Text

1 to Updated Final Safety Analysis Report, Chapter 14.4, Table 14.4.2-1A, Equipment Required to Shutdown Reactor (Unit 2)
	ML22340A161
Person / Time
Site:	Cook
Issue date:	11/30/2022
From:	; Indiana Michigan Power Co
To:	; Office of Nuclear Reactor Regulation
Shared Package
ML22340A137	List: AEP-NRC-2022-62, 1 to Updated Final Safety Analysis Report, Chapter 14.3, Reactor Coolant System Pipe Rupture (Loss of Coolant Accident) (Unit 1); ML22340A128; ML22340A129; ML22340A131; ML22340A132; ML22340A133; ML22340A134; ML22340A135; ML22340A136; ML22340A138; ML22340A139; ML22340A141; ML22340A142; ML22340A143; ML22340A144; ML22340A145; ML22340A146; ML22340A147; ML22340A148; ML22340A149; ML22340A150; ML22340A151; ML22340A152; ML22340A153; ML22340A154; ML22340A155; ML22340A156; ML22340A157; ML22340A158; ML22340A159; ML22340A160; ML22340A161; ML22340A162; ML22340A163; ML22340A164; ML22340A165; ML22340A166; ML22340A167; ML22340A168; ML22340A169; ML22340A170; ML22340A171; ML22340A172; ML22340A173; ML22340A174; ML22340A175; ML22340A176; ML22340A177; ML22340A178; ML22340A179; ... further results
References
	AEP-NRC-2022-62
	Download: ML22340A161 (1)
	v • d • e

UFSAR Revision 31.0 INDIANA MICHIGAN POWER Revised: 27.0 Table: 14.4.2-1 D. C. COOK NUCLEAR PLANT Part 1 of 5 UPDATED FINAL SAFETY ANALYSIS REPORT Page: 1 of 25 Equipment Required to Shutdown Reactor (Unit 2)

(For High Energy Pipe Ruptures Outside the Containment)

Equip Id Equipment Description System Building Elev Room Rm#

Auxiliary CCW Pump Ventilation 12-HV-ACCP-1 Building Auxiliary 633 633 Hallway 633 North Supply Fan Ventilation Auxiliary CCW Pump Ventilation 12-HV-ACCP-2 Building Auxiliary 633 633 Hallway 633 Middle Supply Fan Ventilation Auxiliary CCW Pump Ventilation 12-HV-ACCP-3 Building Auxiliary 633 633 Hallway 633 South Supply Fan Ventilation Unit 2 East Essential Service Water East ESW 12-HV-ESW-1 ESW Ventilation Screenhouse 591 135 Pump Room Supply Ventilation Fan Pump Room Unit 2 East Essential Service Water East ESW 12-HV-ESW-2 ESW Ventilation Screenhouse 591 135 Pump Room Supply Ventilation Fan Pump Room Unit 2 West Essential Service Water West ESW 12-HV-ESW-3 ESW Ventilation Screenhouse 591 136 Pump Room Supply Ventilation Fan Pump Room Unit 2

UFSAR Revision 31.0 INDIANA MICHIGAN POWER Revised: 27.0 Table: 14.4.2-1 D. C. COOK NUCLEAR PLANT Part 1 of 5 UPDATED FINAL SAFETY ANALYSIS REPORT Page: 2 of 25 Equipment Required to Shutdown Reactor (Unit 2)

(For High Energy Pipe Ruptures Outside the Containment)

Equip Id Equipment Description System Building Elev Room Rm#

Unit 2 West Essential Service Water West ESW 12-HV-ESW-4 ESW Ventilation Screenhouse 591 136 Pump Room Supply Ventilation Fan Pump Room Inner Plant 12-TK-47-AB Diesel Fuel Oil Storage Yard Tanks AB Diesel Fuel Oil Grounds 609 244 Grounds Inner Plant 12-TK-47-CD Diesel Fuel Oil Storage Yard Tanks CD Diesel Fuel Oil Grounds 609 244 Grounds 2-20-SV-1-AB Solenoid Valve to POV-1-AB Compressed Air Auxiliary 587 AB EDG Room 121 2-20-SV-1-CD Solenoid Valve to POV-1-CD Compressed Air Auxiliary 587 CD EDG Room 122 2-20-SV-2-AB Solenoid Valve to POV-2-AB Compressed Air Auxiliary 587 AB EDG Room 121 2-20-SV-2-CD Solenoid Valve to POV-2-CD Compressed Air Auxiliary 587 CD EDG Room 122 Unit 2

UFSAR Revision 31.0 INDIANA MICHIGAN POWER Revised: 27.0 Table: 14.4.2-1 D. C. COOK NUCLEAR PLANT Part 1 of 5 UPDATED FINAL SAFETY ANALYSIS REPORT Page: 3 of 25 Equipment Required to Shutdown Reactor (Unit 2)

(For High Energy Pipe Ruptures Outside the Containment)

Equip Id Equipment Description System Building Elev Room Rm#

2-20-SV-3-AB Solenoid Valve to XRV-220 Compressed Air Auxiliary 587 AB EDG Room 121 2-20-SV-3-CD Solenoid Valve to XRV-225 Compressed Air Auxiliary 587 CD EDG Room 122 4kv Room -

2-21A 600Vac Bus 21A 600Vac Auxiliary 609 600v Switchgear 204 Area 4kv Room -

2-21A11 600Vac Bus 21A Supply Breaker 600Vac Auxiliary 609 600v Switchgear 204 Area 4kv Room -

2-21A2 600Vac MCC AM-A Supply Breaker 600Vac Auxiliary 609 600v Switchgear 204 Area 4kv Room -

2-21A5 600Vac MCC ABD-A Supply Breaker 600Vac Auxiliary 609 600v Switchgear 204 Area Unit 2

UFSAR Revision 31.0 INDIANA MICHIGAN POWER Revised: 27.0 Table: 14.4.2-1 D. C. COOK NUCLEAR PLANT Part 1 of 5 UPDATED FINAL SAFETY ANALYSIS REPORT Page: 4 of 25 Equipment Required to Shutdown Reactor (Unit 2)

(For High Energy Pipe Ruptures Outside the Containment)

Equip Id Equipment Description System Building Elev Room Rm#

4kv Room -

600Vac MCCs AB-A, PS-A, TPP-A, and 2-21A6 600Vac Auxiliary 609 600v Switchgear 204 VCCS ABV-A, AZV-A Supply Breaker Area 4kv Room -

2-21A9 600Vac MCC EZC-A Supply Breaker 600Vac Auxiliary 609 600v Switchgear 204 Area 4kv Room -

2-21B 600Vac Bus 21B Supply Breaker 600Vac Auxiliary 609 600v Switchgear 204 Area 4kv Room -

600Vac MCC ABD-B Supply Breaker 2-21B1 600Vac Auxiliary 609 600v Switchgear 204 (2-ELSC)

Area 4kv Room -

2-21B11 600Vac Bus 21B Supply Breaker 600Vac Auxiliary 609 600v Switchgear 204 Area Unit 2

UFSAR Revision 31.0 INDIANA MICHIGAN POWER Revised: 27.0 Table: 14.4.2-1 D. C. COOK NUCLEAR PLANT Part 1 of 5 UPDATED FINAL SAFETY ANALYSIS REPORT Page: 5 of 25 Equipment Required to Shutdown Reactor (Unit 2)

(For High Energy Pipe Ruptures Outside the Containment)

Equip Id Equipment Description System Building Elev Room Rm#

4kv Room -

2-21B2 600Vac MCC EZC-B Supply Breaker 600Vac Auxiliary 609 600v Switchgear 204 Area 4kv Room -

2-21C 600Vac Bus 21C 600Vac Auxiliary 609 600v Switchgear 204 Area 4kv Room -

2-21C1 600v Bus 21C Supply Breaker 600Vac Auxiliary 609 600v Switchgear 204 Area 4kv Room -

600Vac MCC ABD-C and 2-21C10 600Vac Auxiliary 609 600v Switchgear 204 2-AFW Supply Breaker Area 4kv Room -

2-21C6 600Vac MCC EZC-C Supply Breaker 600Vac Auxiliary 609 600v Switchgear 204 Area Unit 2

UFSAR Revision 31.0 INDIANA MICHIGAN POWER Revised: 27.0 Table: 14.4.2-1 D. C. COOK NUCLEAR PLANT Part 1 of 5 UPDATED FINAL SAFETY ANALYSIS REPORT Page: 6 of 25 Equipment Required to Shutdown Reactor (Unit 2)

(For High Energy Pipe Ruptures Outside the Containment)

Equip Id Equipment Description System Building Elev Room Rm#

4kv Room -

2-21D 600Vac Bus 21D 600Vac Auxiliary 609 600v Switchgear 204 Area 4kv Room -

2-21D1 600v Bus 21D Supply Breaker 600Vac Auxiliary 609 600v Switchgear 204 Area 4kv Room -

600Vac MCC 2-AB-D, VCC 2-ABV-D, 2-21D14 600Vac Auxiliary 609 600v Switchgear 204 MCC 2-PS-D Supply Breaker Area 4kv Room -

2-21D5 600Vac MCC ABD-D Supply Breaker 600Vac Auxiliary 609 600v Switchgear 204 Area 4kv Room -

2-21D6 600Vac MCC EZC-D Supply Breaker 600Vac Auxiliary 609 600v Switchgear 204 Area Unit 2

UFSAR Revision 31.0 INDIANA MICHIGAN POWER Revised: 27.0 Table: 14.4.2-1 D. C. COOK NUCLEAR PLANT Part 1 of 5 UPDATED FINAL SAFETY ANALYSIS REPORT Page: 7 of 25 Equipment Required to Shutdown Reactor (Unit 2)

(For High Energy Pipe Ruptures Outside the Containment)

Equip Id Equipment Description System Building Elev Room Rm#

4kv Room -

2-21D8 600Vac MCC AM-D Supply Breaker 600Vac Auxiliary 609 600v Switchgear 204 Area Control Rod Reactor Trip Reactor Rod Control TR-A Reactor Trip Drive 2-52-BYA Breaker (Rod Auxiliary 609 203 Bypass Circuit Breaker Equipment Control & Inst.)

Room Control Rod Reactor Trip Reactor Rod Control Train B Reactor Trip Drive 2-52-BYB Breaker (Rod Auxiliary 609 203 Bypass Circuit Breaker Equipment Control & Inst.)

Room Control Rod Reactor Rod Control Train 'A' Reactor Rod Control and Drive 2-52-RTA Auxiliary 609 203 Trip Circuit Breaker Instrumentation Equipment Room Unit 2

UFSAR Revision 31.0 INDIANA MICHIGAN POWER Revised: 27.0 Table: 14.4.2-1 D. C. COOK NUCLEAR PLANT Part 1 of 5 UPDATED FINAL SAFETY ANALYSIS REPORT Page: 8 of 25 Equipment Required to Shutdown Reactor (Unit 2)

(For High Energy Pipe Ruptures Outside the Containment)

Equip Id Equipment Description System Building Elev Room Rm#

Control Rod Reactor Rod Control Train 'B' Reactor Trip Rod Control and Drive 2-52-RTB Auxiliary 609 203 Circuit Breaker Instrumentation Equipment Room 2-AB-A 600Vac Motor Control Center AB-A 600Vac Auxiliary 587 587 Hallway 587 2-AB-D 600Vac Motor Control Center AB-D 600Vac Auxiliary 587 587 Hallway 587 2-ABD-A 600Vac Motor Control Center ABD-A 600Vac Auxiliary 587 AB EDG Room 121 2-ABD-B 600Vac Motor Control Center ABD-B 600Vac Auxiliary 587 AB EDG Room 121 2-ABD-C 600Vac Motor Control Center ABD-C 600Vac Auxiliary 587 CD EDG Room 122 2-ABD-D 600Vac Motor Control Center ABD-D 600Vac Auxiliary 587 CD EDG Room 122 Unit 2

UFSAR Revision 31.0 INDIANA MICHIGAN POWER Revised: 27.0 Table: 14.4.2-1 D. C. COOK NUCLEAR PLANT Part 1 of 5 UPDATED FINAL SAFETY ANALYSIS REPORT Page: 9 of 25 Equipment Required to Shutdown Reactor (Unit 2)

(For High Energy Pipe Ruptures Outside the Containment)

Equip Id Equipment Description System Building Elev Room Rm#

250Vdc Control 2-AB-N Control Center Valve and Auxiliary 587 587 Hallway 587 Instrumentation 2-ABV-A 600Vac Valve Control Center ABV-A 600Vac Auxiliary 587 587 Hallway 587 2-ABV-D 600Vac Valve Control Center ABV-D 600Vac Auxiliary 587 587 Hallway 587 120/208Vac Misc Safety 2-AFW 120/208 Vac AFW Distribution Panel Auxiliary 587 CD EDG Room 122 Related Power Distribution 120/208Vac 120/208 Vac AFW Auxiliary Distribution Misc Safety 2-AFWX Auxiliary 587 CD EDG Room 122 Panel Related Power Distribution 2-AM-A 600Vac Motor Control Center AM-A 600Vac Auxiliary 633 633 Hallway 633 Unit 2

UFSAR Revision 31.0 INDIANA MICHIGAN POWER Revised: 27.0 Table: 14.4.2-1 D. C. COOK NUCLEAR PLANT Part 1 of 5 UPDATED FINAL SAFETY ANALYSIS REPORT Page: 10 of 25 Equipment Required to Shutdown Reactor (Unit 2)

(For High Energy Pipe Ruptures Outside the Containment)

Equip Id Equipment Description System Building Elev Room Rm#

2-AM-D 600Vac Motor Control Center AM-D 600Vac Auxiliary 633 633 Hallway 633 120/208Vac Reactor Protection Train 'A' Auxiliary Misc Safety 2-ARA-2 Auxiliary 633 Control Room 123 Relay Cabinet #2 Related Power Distribution 120/208Vac Reactor Protection Train 'B' Auxiliary Misc Safety 2-ARB-2 Auxiliary 633 Control Room 123 Relay Cabinet #2 Related Power Distribution 2-AZV-A 600Vac Valve Control Center AZV-A 600Vac Auxiliary 609 609 Hallway 609 AB BATT Equip 2-BATT-AB Plant Battery AB 250Vdc Auxiliary 609 200 Area Plant Battery BATT-AB 4kv Room -

2-BATT-AB-SH 250Vdc Auxiliary 613 205 Ammeter Shunt Mezzanine Area Unit 2

UFSAR Revision 31.0 INDIANA MICHIGAN POWER Revised: 27.0 Table: 14.4.2-1 D. C. COOK NUCLEAR PLANT Part 1 of 5 UPDATED FINAL SAFETY ANALYSIS REPORT Page: 11 of 25 Equipment Required to Shutdown Reactor (Unit 2)

(For High Energy Pipe Ruptures Outside the Containment)

Equip Id Equipment Description System Building Elev Room Rm#

CD BATT 2-BATT-CD Plant Battery CD 250Vdc Auxiliary 626 201 Equip Area Plant Battery BATT-CD CD BATT 2-BATT-CD-SH 250Vdc Auxiliary 626 201 Ammeter Shunt Cabinet Equip Area Plant Battery 250Vdc Control Train 'N' 2-BATT-N Train 'N' Plant Battery and Auxiliary 633 Auxiliary 263 Instrumentation Equipment Room 250Vdc Control Train 'N' Plant Battery 2-BATT-N-SH and Auxiliary 633 633 Hallway 633 Ammeter Shunt Cabinet Instrumentation 250Vdc Control 2-BC-A Battery Charger A for N-Train Battery and Auxiliary 633 633 Hallway 633 Instrumentation Plant Battery BATT-AB 4kv Room -

2-BC-AB1 250Vdc Auxiliary 613 205 Battery Charger #1 Mezzanine Area Unit 2

UFSAR Revision 31.0 INDIANA MICHIGAN POWER Revised: 27.0 Table: 14.4.2-1 D. C. COOK NUCLEAR PLANT Part 1 of 5 UPDATED FINAL SAFETY ANALYSIS REPORT Page: 12 of 25 Equipment Required to Shutdown Reactor (Unit 2)

(For High Energy Pipe Ruptures Outside the Containment)

Equip Id Equipment Description System Building Elev Room Rm#

Plant Battery BATT-AB 4kv Room -

2-BC-AB2 250Vdc Auxiliary 613 205 Charger #2 Mezzanine Area Plant Battery Charger 4kv Room -

2-BC-AB-SH 250Vdc Auxiliary 613 205 Ammeter BC-AB Shunt Cabinet Mezzanine Area 250Vdc Control 2-BC-B Battery Charger B for N-Train Battery and Auxiliary 633 633 Hallway 633 Instrumentation CD BATT Equip 2-BC-CD1 Plant Battery BATT-CD Charger #1 250Vdc Auxiliary 626 201 Area CD BATT 2-BC-CD2 Plant Battery BATT-CD Charger #2 250Vdc Auxiliary 626 201 Equip Area Plant Battery Charger CD BATT 2-BC-CD-SH 250Vdc Auxiliary 626 201 BC-CD Shunt Cabinet Equip Area Plant Battery Chargers BC-AB1 and BC- 4kv Room -

2-BCTC-AB 250Vdc Auxiliary 613 205 AB2 Transfer Switch Cabinet Mezzanine Area Unit 2

UFSAR Revision 31.0 INDIANA MICHIGAN POWER Revised: 27.0 Table: 14.4.2-1 D. C. COOK NUCLEAR PLANT Part 1 of 5 UPDATED FINAL SAFETY ANALYSIS REPORT Page: 13 of 25 Equipment Required to Shutdown Reactor (Unit 2)

(For High Energy Pipe Ruptures Outside the Containment)

Equip Id Equipment Description System Building Elev Room Rm#

Plant Battery Chargers CD BATT Equip 2-BCTC-CD 250Vdc Auxiliary 626 201 BC-CD1 and BC-CD2 Transfer Cabinet Area Steam Generator OME-3-1 Accumulator 2-BLI-110 Main Steam Containment 612 68 Wide Range Level Indicator Transmitter Tank #1 Area West Steam Generator OME-3-2 Containment 2-BLI-120 Main Steam Containment 612 73 Wide Range Level Indicator Transmitter Lower Vent Room Steam Generator OME-3-3 Accumulator 2-BLI-130 Main Steam Containment 612 70 Wide Range Level Indicator Transmitter Tank #3 Area Steam Generator OME-3-4 Accumulator 2-BLI-140 Main Steam Containment 612 71 Wide Range Level Indicator Transmitter Tank #4 Area Steam Generator OME-3-1 Accumulator 2-BLP-110 Channel 4 Reactor Protection Input Main Steam Containment 612 68 Tank #1 Area Narrow Range Level Transmitter Unit 2

UFSAR Revision 31.0 INDIANA MICHIGAN POWER Revised: 27.0 Table: 14.4.2-1 D. C. COOK NUCLEAR PLANT Part 1 of 5 UPDATED FINAL SAFETY ANALYSIS REPORT Page: 14 of 25 Equipment Required to Shutdown Reactor (Unit 2)

(For High Energy Pipe Ruptures Outside the Containment)

Equip Id Equipment Description System Building Elev Room Rm#

East Steam Generator OME-3-1 Containment 2-BLP-111 Channel 2 Reactor Protection Input Main Steam Containment 612 72 Lower Vent Narrow Range Level Transmitter Room East Steam Generator OME-3-1 Containment 2-BLP-112 Channel 3 Reactor Protection Input Main Steam Containment 612 72 Lower Vent Narrow Range Level Transmitter Room West Steam Generator OME-3-2 Containment 2-BLP-120 Channel 4 Reactor Protection Input Main Steam Containment 612 73 Lower Vent Narrow Range Level Transmitter Room West Steam Generator OME-3-2 Containment 2-BLP-121 Channel 1 Reactor Protection Input Main Steam Containment 612 73 Lower Vent Narrow Range Level Transmitter Room Unit 2

UFSAR Revision 31.0 INDIANA MICHIGAN POWER Revised: 27.0 Table: 14.4.2-1 D. C. COOK NUCLEAR PLANT Part 1 of 5 UPDATED FINAL SAFETY ANALYSIS REPORT Page: 15 of 25 Equipment Required to Shutdown Reactor (Unit 2)

(For High Energy Pipe Ruptures Outside the Containment)

Equip Id Equipment Description System Building Elev Room Rm#

Steam Generator OME-3-2 Accumulator 2-BLP-122 Channel 3 Reactor Protection Input Main Steam Containment 612 69 Tank #2 Area Narrow Range Level Transmitter West Steam Generator OME-3-3 Containment 2-BLP-130 Channel 4 Reactor Protection Input Main Steam Containment 612 73 Lower Vent Narrow Range Level Transmitter Room West Steam Generator OME-3-3 Containment 2-BLP-131 Channel 1 Reactor Protection Input Main Steam Containment 612 73 Lower Vent Narrow Range Level Transmitter Room West Steam Generator OME-3-3 Containment 2-BLP-132 Channel 3 Reactor Protection Input Main Steam Containment 612 73 Lower Vent Narrow Range Level Transmitter Room Unit 2

UFSAR Revision 31.0 INDIANA MICHIGAN POWER Revised: 27.0 Table: 14.4.2-1 D. C. COOK NUCLEAR PLANT Part 1 of 5 UPDATED FINAL SAFETY ANALYSIS REPORT Page: 16 of 25 Equipment Required to Shutdown Reactor (Unit 2)

(For High Energy Pipe Ruptures Outside the Containment)

Equip Id Equipment Description System Building Elev Room Rm#

East Steam Generator OME-3-4 Containment 2-BLP-140 Channel 4 Reactor Protection Input Main Steam Containment 612 72 Lower Vent Narrow Range Level Transmitter Room East Steam Generator OME-3-4 Containment 2-BLP-141 Channel 2 Reactor Protection Input Main Steam Containment 612 72 Lower Vent Narrow Range Level Transmitter Room Steam Generator OME-3-4 Accumulator 2-BLP-142 Channel 3 Reactor Protection Input Main Steam Containment 612 71 Tank #4 Area Narrow Range Level Transmitter Containment 85 PSI Lower 2-CA-711 Control Air Ring Header #2 to Control Control Air Containment 625 Containment, 63 Valve NRV-152 Check Valve Quadrant #4 Containment 85 PSI Lower 2-CA-713 Control Air Ring Header to Control Valve Control Air Containment 625 Containment, 63 NRV-153 Check Valve Quadrant #4 Unit 2

UFSAR Revision 31.0 INDIANA MICHIGAN POWER Revised: 27.0 Table: 14.4.2-1 D. C. COOK NUCLEAR PLANT Part 1 of 5 UPDATED FINAL SAFETY ANALYSIS REPORT Page: 17 of 25 Equipment Required to Shutdown Reactor (Unit 2)

(For High Energy Pipe Ruptures Outside the Containment)

Equip Id Equipment Description System Building Elev Room Rm#

Containment Auxiliaries Subpanel Containment 2-CAS Auxiliary 633 633 Hallway 633 (Ventilation) Ventilation 250Vdc Train 'B' 2-CCV-AB 250Vdc Auxiliary 633 Control Room 123 Critical Solenoid Valves Distribution Panel 250Vdc Train 'A' 2-CCV-CD 250Vdc Auxiliary 633 Control Room 123 Critical Solenoid Valves Distribution Panel Unit 2

UFSAR Revision 31.0 INDIANA MICHIGAN POWER Revised: 27.0 Table: 14.4.2-1 D. C. COOK NUCLEAR PLANT Part 1 of 5 UPDATED FINAL SAFETY ANALYSIS REPORT Page: 18 of 25 Equipment Required to Shutdown Reactor (Unit 2)

(For High Energy Pipe Ruptures Outside the Containment)

Equip Id Equipment Description System Building Elev Room Rm#

Unit 2

UFSAR Revision 31.0 INDIANA MICHIGAN POWER Revised: 27.0 Table: 14.4.2-1 D. C. COOK NUCLEAR PLANT Part 1 of 5 UPDATED FINAL SAFETY ANALYSIS REPORT Page: 19 of 25 Equipment Required to Shutdown Reactor (Unit 2)

(For High Energy Pipe Ruptures Outside the Containment)

Equip Id Equipment Description System Building Elev Room Rm#

East CCW Heat Exchanger HE-15E CCW Component 2-CMO-410 Auxiliary 609 609 Hallway 609 Outlet Shutoff Valve Cooling Water CCW Pumps Suction Crosstie Train 'A' Component 2-CMO-411 Auxiliary 609 609 Hallway 609 Misc. Service Shutoff Valve Cooling Water CCW Pumps Discharge Component 2-CMO-412 Auxiliary 609 609 Hallway 609 Crosstie Train 'A' Shutoff Valve Cooling Water CCW Pumps Suction Crosstie Train 'B' Component 2-CMO-413 Auxiliary 609 609 Hallway 609 Misc. Service Shutoff Valve Cooling Water CCW Pumps Discharge Component 2-CMO-414 Auxiliary 609 609 Hallway 609 Crosstie Train 'B' Shutoff Valve Cooling Water CCW to Miscellaneous Service Component 2-CMO-415 Auxiliary 609 609 Hallway 609 Train 'A' Shutoff Valve Cooling Water Unit 2

UFSAR Revision 31.0 INDIANA MICHIGAN POWER Revised: 27.0 Table: 14.4.2-1 D. C. COOK NUCLEAR PLANT Part 1 of 5 UPDATED FINAL SAFETY ANALYSIS REPORT Page: 20 of 25 Equipment Required to Shutdown Reactor (Unit 2)

(For High Energy Pipe Ruptures Outside the Containment)

Equip Id Equipment Description System Building Elev Room Rm#

CCW to Miscellaneous Service Header 'B' Component 2-CMO-416 Auxiliary 609 609 Hallway 609 16" Motor Operated Shutoff Valve Cooling Water East RHR Heat Exchanger HE-17E CCW Component 2-CMO-419 Auxiliary 609 609 Hallway 609 Outlet Shutoff Valve Cooling Water West CCW Heat Exchanger HE-15W Component 2-CMO-420 Auxiliary 609 609 Hallway 609 CCW Outlet Shutoff Valve Cooling Water West RHR Heat Exchanger HE-17W Component 2-CMO-429 Auxiliary 633 633 Hallway 633 CCW Outlet Shutoff Valve Cooling Water AB Emergency Diesel Diesel Jacket 2-CPS-312 Jacket Water Pump QT-130-AB1 Auxiliary 587 AB EDG Room 121 Water Discharge Pressure Switch AB Emergency Diesel Diesel Jacket 2-CPS-314 Jacket Water Pump QT-130-AB2 Auxiliary 587 AB EDG Room 121 Water Discharge Pressure Switch Unit 2

UFSAR Revision 31.0 INDIANA MICHIGAN POWER Revised: 27.0 Table: 14.4.2-1 D. C. COOK NUCLEAR PLANT Part 1 of 5 UPDATED FINAL SAFETY ANALYSIS REPORT Page: 21 of 25 Equipment Required to Shutdown Reactor (Unit 2)

(For High Energy Pipe Ruptures Outside the Containment)

Equip Id Equipment Description System Building Elev Room Rm#

CD Emergency Diesel Diesel Jacket 2-CPS-317 Jacket Water Pump QT-130-CD1 Auxiliary 587 CD EDG Room 122 Water Discharge Pressure Switch CD Emergency Diesel Diesel Jacket 2-CPS-319 Jacket Water Pump QT-130-CD2 Auxiliary 587 CD EDG Room 122 Water Discharge Pressure Switch East Component Cooling Water Component 2-CPS-410 Auxiliary 609 609 Hallway 609 Pump PP-10E Discharge Pressure Switch Cooling Water West Component Cooling Water Component 2-CPS-420 Auxiliary 609 609 Hallway 609 Pump PP-10w Discharge Pressure Switch Cooling Water 250Vdc Control Room Distribution Panel 2-CRAB 250Vdc Auxiliary 633 Control Room 123 CRAB 250Vdc Control Room Distribution Panel 2-CRCD 250Vdc Auxiliary 633 Control Room 123 CRCD Unit 2

UFSAR Revision 31.0 INDIANA MICHIGAN POWER Revised: 27.0 Table: 14.4.2-1 D. C. COOK NUCLEAR PLANT Part 1 of 5 UPDATED FINAL SAFETY ANALYSIS REPORT Page: 22 of 25 Equipment Required to Shutdown Reactor (Unit 2)

(For High Energy Pipe Ruptures Outside the Containment)

Equip Id Equipment Description System Building Elev Room Rm#

120Vac Control 120Vac Control Room Instrument Room 2-CRID-I Auxiliary 633 Control Room 123 Distribution Channel I Distribution Panel Instrumentation Distr 120Vac Control 120Vac Control Room Instrument 4kv Room -

Room 2-CRID-I-CVT Distribution Channel I Constant Voltage Auxiliary 609 600v Switchgear 204 Instrumentation Transformer Area Distr 120Vac Control 120Vac Control Room Instrument Room 2-CRID-II Auxiliary 633 Control Room 123 Distribution Channel II Distribution Panel Instrumentation Distr 120Vac Control 120Vac Control Room Instrument 4kv Room -

Room 2-CRID-II-CVT Distribution Channel II Constant Voltage Auxiliary 609 600v Switchgear 204 Instrumentation Transformer Area Distr Unit 2

UFSAR Revision 31.0 INDIANA MICHIGAN POWER Revised: 27.0 Table: 14.4.2-1 D. C. COOK NUCLEAR PLANT Part 1 of 5 UPDATED FINAL SAFETY ANALYSIS REPORT Page: 23 of 25 Equipment Required to Shutdown Reactor (Unit 2)

(For High Energy Pipe Ruptures Outside the Containment)

Equip Id Equipment Description System Building Elev Room Rm#

120Vac Control 120Vac Control Room Instrument Room 2-CRID-III Auxiliary 633 Control Room 123 Distribution Channel III Distribution Panel Instrumentation Distr 120Vac Control 120Vac Control Room Instrument 4kv Room -

Room 2-CRID-III-CVT Distribution Channel III Constant Voltage Auxiliary 609 600v Switchgear 204 Instrumentation Transformer Area Distr 120Vac Control 120Vac Control Room Instrumentation Room 2-CRID-III-INV Auxiliary 609 Inverter Area 202 Distribution System Channel III Inverter Instrumentation Distr 120Vac Control 120Vac Control Room Instrument Room 2-CRID-II-INV Auxiliary 609 Inverter Area 202 Distribution System Channel II Inverter Instrumentation Distr Unit 2

UFSAR Revision 31.0 INDIANA MICHIGAN POWER Revised: 27.0 Table: 14.4.2-1 D. C. COOK NUCLEAR PLANT Part 1 of 5 UPDATED FINAL SAFETY ANALYSIS REPORT Page: 24 of 25 Equipment Required to Shutdown Reactor (Unit 2)

(For High Energy Pipe Ruptures Outside the Containment)

Equip Id Equipment Description System Building Elev Room Rm#

120Vac Control 120Vac Control Room Instrument Room 2-CRID-I-INV Auxiliary 609 Inverter Area 202 Distribution System Channel I Inverter Instrumentation Distr 120Vac Control 120Vac Control Room Instrument Room 2-CRID-IV Auxiliary 633 Control Room 123 Distribution Channel IV Distribution Panel Instrumentation Distr 120Vac Control 120Vac Control Room Instrument 4kv Room -

Room 2-CRID-IV-CVT Distribution Channel IV Constant Voltage Auxiliary 609 600v Switchgear 204 Instrumentation Transformer Area Distr 120Vac Control 120Vac Control Room Instrument Room 2-CRID-IV-INV Auxiliary 609 Control Room 123 Distribution System Channel IV Inverter Instrumentation Distr Unit 2

UFSAR Revision 31.0 INDIANA MICHIGAN POWER Revised: 27.0 Table: 14.4.2-1 D. C. COOK NUCLEAR PLANT Part 1 of 5 UPDATED FINAL SAFETY ANALYSIS REPORT Page: 25 of 25 Equipment Required to Shutdown Reactor (Unit 2)

(For High Energy Pipe Ruptures Outside the Containment)

Equip Id Equipment Description System Building Elev Room Rm#

Reciprocating CVCS Reciprocating Charging Pump (CVCS) 2-CS-304 Auxiliary 587 Charging Pump 39 Inlet Isolation Valve Charging Room Reciprocating CVCS Reciprocating Charging Pump (CVCS) 2-CS-306 Auxiliary 587 Charging Pump 39 Outlet Isolation Valve Charging Room Unit 2

UFSAR Revision 31.0 INDIANA MICHIGAN POWER Revised: 26.0 Table: 14.4.2-1 D. C. COOK NUCLEAR PLANT Part 2 of 5 UPDATED FINAL SAFETY ANALYSIS REPORT Page: 1 of 23 Equipment Required to Shutdown Reactor (Unit 2)

(For High Energy Pipe Ruptures Outside the Containment)

Equip Id Equipment Description System Building Elev Room Rm#

East Component Cooling Water Component 2-CTR-415 Heat Exchanger HE-15E CCW Outlet Auxiliary 609 609 Hallway 609 Cooling Water Temperature Recorder Thermal Sensor West Component Cooling Water Component 2-CTR-425 Heat Exchanger CCW Outlet Temperature Auxiliary 609 609 Hallway 609 Cooling Water Recorder Thermal Sensor 250Vdc Control 2-DCN 250Vdc Distribution Panel DCN and Auxiliary 633 633 Hallway 633 Instrumentation Startup Steam Generator OME-3-1 2-DCR-310 Blowdown Auxiliary 591 Blowdown 29 Blowdown Containment Isolation Valve Flashtank Room Startup Steam Generator OME-3-2 2-DCR-320 Blowdown Auxiliary 591 Blowdown 29 Blowdown Containment Isolation Valve Flashtank Room Unit 2

UFSAR Revision 31.0 INDIANA MICHIGAN POWER Revised: 26.0 Table: 14.4.2-1 D. C. COOK NUCLEAR PLANT Part 2 of 5 UPDATED FINAL SAFETY ANALYSIS REPORT Page: 2 of 23 Equipment Required to Shutdown Reactor (Unit 2)

(For High Energy Pipe Ruptures Outside the Containment)

Equip Id Equipment Description System Building Elev Room Rm#

Startup Steam Generator OME-3-3 2-DCR-330 Blowdown Auxiliary 591 Blowdown 29 Blowdown Containment Isolation Valve Flashtank Room Startup Steam Generator OME-3-4 2-DCR-340 Blowdown Auxiliary 591 Blowdown 29 Blowdown Containment Isolation Valve Flashtank Room AB Emergency Diesel Diesel Starting 2-DG-102A Starting Air Compressor QT-142-AB2 Auxiliary 587 AB EDG Room 121 Air Outlet Check Valve CD Emergency Diesel Diesel Starting 2-DG-102C Starting Air Compressor QT-142-CD2 Auxiliary 587 CD EDG Room 122 Air Outlet Check Valve AB Emergency Diesel Diesel Starting 2-DG-104A Starting Air Compressor QT-142-AB1 Auxiliary 587 AB EDG Room 121 Air Outlet Check Valve Unit 2

UFSAR Revision 31.0 INDIANA MICHIGAN POWER Revised: 26.0 Table: 14.4.2-1 D. C. COOK NUCLEAR PLANT Part 2 of 5 UPDATED FINAL SAFETY ANALYSIS REPORT Page: 3 of 23 Equipment Required to Shutdown Reactor (Unit 2)

(For High Energy Pipe Ruptures Outside the Containment)

Equip Id Equipment Description System Building Elev Room Rm#

CD Emergency Diesel Diesel Starting 2-DG-104C Starting Air Compressor QT-142-CD1 Auxiliary 587 CD EDG Room 122 Air Outlet Check Valve Diesel AB Emergency Diesel Generator, 2-DGAB Auxiliary 587 AB EDG Room 121 Generator OME-150-AB Control Subpanel Control &

Instrumentation Diesel AB Emergency Diesel Generator, 2-DGAB-FFCKT Generator OME-150-AB Field Flash Auxiliary 587 AB EDG Room 121 Control &

Circuit Transformer Instrumentation Diesel AB Emergency Diesel Generator, 2-DGAB-INV Auxiliary 587 AB EDG Room 121 Generator OME-150-AB Inverter Control &

Instrumentation Unit 2

UFSAR Revision 31.0 INDIANA MICHIGAN POWER Revised: 26.0 Table: 14.4.2-1 D. C. COOK NUCLEAR PLANT Part 2 of 5 UPDATED FINAL SAFETY ANALYSIS REPORT Page: 4 of 23 Equipment Required to Shutdown Reactor (Unit 2)

(For High Energy Pipe Ruptures Outside the Containment)

Equip Id Equipment Description System Building Elev Room Rm#

Diesel Equip Ctrl and Indication STN/AB Generator, 2-DGAB-X Emergency Diesel Generator 150 Aux Auxiliary 587 AB EDG Room 121 Control &

Panel Instrumentation Diesel CD Emergency Diesel Generator, 2-DGCD Auxiliary 587 CD EDG Room 122 Generator OME-150-CD Control Subpanel Control &

Instrumentation Diesel CD Emergency Diesel Generator, 2-DGCD-FFCKT Generator OME-150-CD Field Flash CKT Auxiliary 587 CD EDG Room 122 Control &

Transformer Instrumentation Diesel CD Emergency Diesel Generator, 2-DGCD-INV Auxiliary 587 CD EDG Room 122 Generator OME-150-CD Inverter Control &

Instrumentation Unit 2

UFSAR Revision 31.0 INDIANA MICHIGAN POWER Revised: 26.0 Table: 14.4.2-1 D. C. COOK NUCLEAR PLANT Part 2 of 5 UPDATED FINAL SAFETY ANALYSIS REPORT Page: 5 of 23 Equipment Required to Shutdown Reactor (Unit 2)

(For High Energy Pipe Ruptures Outside the Containment)

Equip Id Equipment Description System Building Elev Room Rm#

Diesel Equip Ctrl and Indication STN/CD Generator, 2-DGCD-X Emergency Diesel Generator 150 Aux Auxiliary 587 CD EDG Room 122 Control &

Panel Instrumentation Control Room Vent North Chill Water Control Room Control Rm A/C 2-DW-163N Auxiliary 650 129 Circulation Manual Isolation Valve Ventilation Room Control Room Vent South Chill Water Control Room Control Rm A/C 2-DW-163S Auxiliary 650 129 Circulation Manual Isolation Valve Ventilation Room 120/208Vac 120/208 Vac Emergency Local Shutdown Misc Safety 2-ELSC Auxiliary 587 AB EDG Room 121 Distribution Panel Related Power Distribution 120/208Vac 120/208Vac Emergency Local Shutdown Misc Safety 2-ELSCX Auxiliary 587 AB EDG Room 121 Auxiliary Distribution Panel Related Power Distribution Unit 2

UFSAR Revision 31.0 INDIANA MICHIGAN POWER Revised: 26.0 Table: 14.4.2-1 D. C. COOK NUCLEAR PLANT Part 2 of 5 UPDATED FINAL SAFETY ANALYSIS REPORT Page: 6 of 23 Equipment Required to Shutdown Reactor (Unit 2)

(For High Energy Pipe Ruptures Outside the Containment)

Equip Id Equipment Description System Building Elev Room Rm#

ESW Supply Valve to Turbine-Driven Essential Service 2-ESW-240 Turbine 591 TDAFP Room 49 AFW Pump PP-4 Water ESW Supply Valve to Motor-Driven AFW Essential Service West MDAFP 2-ESW-243 Turbine 591 51 Pump PP-3W Water Room 4kv Room -

2-EZC-A 600Vac Motor Control Center EZC-A 600Vac Auxiliary 613 205 Mezzanine Area 4kv Room -

2-EZC-B 600Vac Motor Control Center EZC-B 600Vac Auxiliary 613 205 Mezzanine Area 4kv Room -

2-EZC-C 600Vac Motor Control Center EZC-C 600Vac Auxiliary 613 205 Mezzanine Area 4kv Room -

2-EZC-D 600Vac Motor Control Center EZC-D 600Vac Auxiliary 613 205 Mezzanine Area Feedwater to Steam Generator #1 East Main Steam 2-FFC-210 Feedwater Auxiliary 621 10 Channel I Flow Control Transmitter Stop Enclosure Feedwater to Steam Generator #1 East Main Steam 2-FFC-211 Feedwater Auxiliary 621 11 Channel II Flow Control Transmitter Stop Enclosure Unit 2

UFSAR Revision 31.0 INDIANA MICHIGAN POWER Revised: 26.0 Table: 14.4.2-1 D. C. COOK NUCLEAR PLANT Part 2 of 5 UPDATED FINAL SAFETY ANALYSIS REPORT Page: 7 of 23 Equipment Required to Shutdown Reactor (Unit 2)

(For High Energy Pipe Ruptures Outside the Containment)

Equip Id Equipment Description System Building Elev Room Rm#

West Feedwater Feedwater to Steam Generator #2 2-FFC-220 Feedwater Auxiliary 587 Regulating 48 Channel I Flow Control Transmitter Valve Area West Feedwater Feedwater to Steam Generator #2 2-FFC-221 Feedwater Auxiliary 587 Regulating 48 Channel II Flow Control Transmitter Valve Area West Feedwater Feedwater to Steam Generator #3 2-FFC-230 Feedwater Auxiliary 587 Regulating 48 Channel I Flow Control Transmitter Valve Area West Feedwater Feedwater to Steam Generator #3 2-FFC-231 Feedwater Auxiliary 587 Regulating 48 Channel II Flow Control Transmitter Valve Area East Feedwater Feedwater to Steam Generator #4 2-FFC-240 Feedwater Auxiliary 612 Regulating 13 Channel I Flow Control Transmitter Valve Area Unit 2

UFSAR Revision 31.0 INDIANA MICHIGAN POWER Revised: 26.0 Table: 14.4.2-1 D. C. COOK NUCLEAR PLANT Part 2 of 5 UPDATED FINAL SAFETY ANALYSIS REPORT Page: 8 of 23 Equipment Required to Shutdown Reactor (Unit 2)

(For High Energy Pipe Ruptures Outside the Containment)

Equip Id Equipment Description System Building Elev Room Rm#

East Feedwater Feedwater to Steam Generator #4 2-FFC-241 Feedwater Auxiliary 612 Regulating 13 Channel II Flow Control Transmitter Valve Area Auxiliary Feedwater to Steam Generator Auxiliary East Main Steam 2-FFI-210 Auxiliary 621 10 OME-3-1 Flow Indicator Transmitter Feedwater Stop Enclosure West Main Auxiliary Feedwater to Steam Generator Auxiliary 2-FFI-220 Auxiliary 621 Steam Stop 9 OME-3-2 Flow Indicator Transmitter Feedwater Enclosure West Main Auxiliary Feedwater to Steam Generator Auxiliary 2-FFI-230 Auxiliary 621 Steam Stop 9 OME-3-3 Flow Indicator Transmitter Feedwater Enclosure Auxiliary Feedwater to Steam Generator Auxiliary East Main Steam 2-FFI-240 Auxiliary 621 10 OME-3-4 Flow Indicator Transmitter Feedwater Stop Enclosure West Motor Driven Auxiliary Feedwater Auxiliary West MDAFP 2-FFS-244 Turbine 591 51 Pump PP-3W Discharge Flow Switch Feedwater Room West Motor Driven Auxiliary Feedwater Auxiliary West MDAFP 2-FFS-245 Turbine 591 51 Pump PP-3W Discharge Flow Switch Feedwater Room Unit 2

UFSAR Revision 31.0 INDIANA MICHIGAN POWER Revised: 26.0 Table: 14.4.2-1 D. C. COOK NUCLEAR PLANT Part 2 of 5 UPDATED FINAL SAFETY ANALYSIS REPORT Page: 9 of 23 Equipment Required to Shutdown Reactor (Unit 2)

(For High Energy Pipe Ruptures Outside the Containment)

Equip Id Equipment Description System Building Elev Room Rm#

Auxiliary Feed East Motor Driven Auxiliary Feedwater Auxiliary 2-FFS-254 Turbine 591 Pump East 83 Pump PP-3E Discharge Flow Switch Feedwater Hallway Auxiliary Feed East Motor Driven Auxiliary Feedwater Auxiliary 2-FFS-255 Turbine 591 Pump East 83 Pump PP-3E Discharge Flow Switch Feedwater Hallway Auxiliary Feed Turbine Driven Auxiliary Feedwater Pump Auxiliary 2-FFS-258 Turbine 591 Pump East 83 PP-4 Discharge Flow Switch Feedwater Hallway Turbine Driven Auxiliary Feedwater Pump Auxiliary 2-FFS-260 Turbine 591 TDAFP Room 49 PP-4 Discharge Flow Switch Feedwater Turbine Driven Auxiliary Feed Pump PP-4 Auxiliary East Main Steam 2-FMO-211 Discharge to Steam Generator OME-3-1 4" Auxiliary 612 10 Feedwater Stop Enclosure Motor Operated Control Valve Unit 2

UFSAR Revision 31.0 INDIANA MICHIGAN POWER Revised: 26.0 Table: 14.4.2-1 D. C. COOK NUCLEAR PLANT Part 2 of 5 UPDATED FINAL SAFETY ANALYSIS REPORT Page: 10 of 23 Equipment Required to Shutdown Reactor (Unit 2)

(For High Energy Pipe Ruptures Outside the Containment)

Equip Id Equipment Description System Building Elev Room Rm#

West Motor Driven Auxiliary Feedwater Pump PP-3W Supply to Steam Generator Auxiliary East Main Steam 2-FMO-212 Auxiliary 612 10 OME-3-1 4" Motor Operated Control Feedwater Stop Enclosure Valve Turbine Driven Auxiliary Feed Pump PP-4 Startup Auxiliary 2-FMO-221 Discharge to Steam Generator OME-3-2 4" Auxiliary 591 Blowdown 29 Feedwater Motor Operated Control Valve Flashtank Room East Motor Driven Auxiliary Feedwater Startup Pump PP-3E Supply to Steam Generator Auxiliary 2-FMO-222 Auxiliary 591 Blowdown 29 OME-3-2 4" Motor Operated Control Feedwater Flashtank Room Valve Turbine Driven Auxiliary Feed Pump PP-4 Startup Auxiliary 2-FMO-231 Supply to Steam Generator OME-3-3 4" Auxiliary 591 Blowdown 29 Feedwater Motor Operated Control Valve Flashtank Room East Motor Driven Auxiliary Feedwater Startup Pump PP-3E Supply to Steam Generator Auxiliary 2-FMO-232 Auxiliary 591 Blowdown 29 OME-3-3 4" Motor Operated Control Feedwater Flashtank Room Valve Unit 2

UFSAR Revision 31.0 INDIANA MICHIGAN POWER Revised: 26.0 Table: 14.4.2-1 D. C. COOK NUCLEAR PLANT Part 2 of 5 UPDATED FINAL SAFETY ANALYSIS REPORT Page: 11 of 23 Equipment Required to Shutdown Reactor (Unit 2)

(For High Energy Pipe Ruptures Outside the Containment)

Equip Id Equipment Description System Building Elev Room Rm#

Turbine Driven Auxiliary Feed Pump PP-4 Auxiliary East Main Steam 2-FMO-241 Supply to Steam Generator OME-3-4 4" Auxiliary 612 10 Feedwater Stop Enclosure Motor Operated Control Valve West Motor Driven Auxiliary Feedwater Pump PP-3W Supply to Steam Generator Auxiliary East Main Steam 2-FMO-242 Auxiliary 612 10 OME-3-4 4" Motor Operated Control Feedwater Stop Enclosure Valve East Feedwater Steam Generator OME-3-1 Feedwater 2-FRV-210 Feedwater Auxiliary 612 Regulating 13 Regulating Valve Valve Area West Feedwater Steam Generator OME-3-2 Feedwater 2-FRV-220 Feedwater Auxiliary 587 Regulating 48 Regulating Valve Valve Area West Feedwater Steam Generator OME-3-3 Feedwater 2-FRV-230 Feedwater Auxiliary 587 Regulating 48 Regulating Valve Valve Area Unit 2

UFSAR Revision 31.0 INDIANA MICHIGAN POWER Revised: 26.0 Table: 14.4.2-1 D. C. COOK NUCLEAR PLANT Part 2 of 5 UPDATED FINAL SAFETY ANALYSIS REPORT Page: 12 of 23 Equipment Required to Shutdown Reactor (Unit 2)

(For High Energy Pipe Ruptures Outside the Containment)

Equip Id Equipment Description System Building Elev Room Rm#

East Feedwater Steam Generator OME-3-4 Feedwater 2-FRV-240 Feedwater Auxiliary 612 Regulating 13 Regulating Valve Valve Area West Motor Driven Auxiliary Feed Pump Auxiliary West MDAFP 2-FRV-245 Turbine 591 51 PP-3W 2" Air Operated Test Valve Feedwater Room West Motor Driven Auxiliary Feed Pump Auxiliary West MDAFP 2-FRV-247 PP-3W Emergency 1" Air Operated Turbine 591 51 Feedwater Room Leakoff Globe Valve East Motor Driven Auxiliary Feedwater Auxiliary East MDAFP 2-FRV-255 Turbine 591 50 Pump PP-3E 2" Air Operated Test Valve Feedwater Room Turbine Driven Auxiliary Feed Pump PP-4 Auxiliary 2-FRV-256 Turbine 591 TDAFP Room 49 2" Air Operated Test Valve Feedwater East Motor Driven Auxiliary Feedwater Auxiliary East MDAFP 2-FRV-257 Pump PP-3E Emergency 1" Air Operated Turbine 591 50 Feedwater Room Leakoff Valve Unit 2

UFSAR Revision 31.0 INDIANA MICHIGAN POWER Revised: 26.0 Table: 14.4.2-1 D. C. COOK NUCLEAR PLANT Part 2 of 5 UPDATED FINAL SAFETY ANALYSIS REPORT Page: 13 of 23 Equipment Required to Shutdown Reactor (Unit 2)

(For High Energy Pipe Ruptures Outside the Containment)

Equip Id Equipment Description System Building Elev Room Rm#

Turbine Driven Auxiliary Feed Pump PP-4 Auxiliary 2-FRV-258 Emergency 1" Air Operated Leakoff Globe Turbine 591 TDAFP Room 49 Feedwater Valve Feedwater to Steam Generator #1 East Main Steam 2-FW-118-1 Feedwater Auxiliary 621 10 Containment Isolation Check Valve Stop Enclosure West Main Feedwater to Steam Generator #2 2-FW-118-2 Feedwater Auxiliary 621 Steam Stop 9 Containment Isolation Check Valve Enclosure West Main Feedwater to Steam Generator #3 2-FW-118-3 Feedwater Auxiliary 621 Steam Stop 9 Containment Isolation Check Valve Enclosure Feedwater to Steam Generator #4 East Main Steam 2-FW-118-4 Feedwater Auxiliary 621 10 Containment Isolation Check Valve Stop Enclosure East Motor Driven Aux Feedwater Auxiliary East MDAFP 2-FW-129 Pump PP-3E Disc to Unit 1 Crosstie Turbine 591 50 Feedwater Room Shutoff Valve Unit 2

UFSAR Revision 31.0 INDIANA MICHIGAN POWER Revised: 26.0 Table: 14.4.2-1 D. C. COOK NUCLEAR PLANT Part 2 of 5 UPDATED FINAL SAFETY ANALYSIS REPORT Page: 14 of 23 Equipment Required to Shutdown Reactor (Unit 2)

(For High Energy Pipe Ruptures Outside the Containment)

Equip Id Equipment Description System Building Elev Room Rm#

Reactor Coolant Seal Water Heat Reactor Coolant Pump Seal Water Heat Pump Seal 2-HE-11 Auxiliary 609 Exchanger 18 Exchanger (Pressure Boundary Only) Water Room INJ/Leakoff Component 2-HE-15E East CCW Heat Exchanger Auxiliary 609 609 Hallway 609 Cooling Water Component 2-HE-15W West CCW Heat Exchanger Auxiliary 609 609 Hallway 609 Cooling Water East RHR Heat East Residual Heat Removal Heat Residual Heat 2-HE-17E Auxiliary 609 Exchanger 5 Exchanger Removal Room West RHR Heat West Residual Heat Removal Heat Residual Heat 2-HE-17W Auxiliary 609 Exchanger 6 Exchanger Removal Room East Residual Heat Removal Pump PP-35E Component East RHR Pump 2-HE-32E Auxiliary 573 54 Mechanical Seal Heat Exchanger Cooling Water Room Unit 2

UFSAR Revision 31.0 INDIANA MICHIGAN POWER Revised: 26.0 Table: 14.4.2-1 D. C. COOK NUCLEAR PLANT Part 2 of 5 UPDATED FINAL SAFETY ANALYSIS REPORT Page: 15 of 23 Equipment Required to Shutdown Reactor (Unit 2)

(For High Energy Pipe Ruptures Outside the Containment)

Equip Id Equipment Description System Building Elev Room Rm#

West Residual Heat Removal Pump PP- Component West RHR 2-HE-32W Auxiliary 573 55 35W Mechanical Seal Heat Exchanger Cooling Water Pump Room North Safety North Safety Injection Pump Mech Seal Component 2-HE-34NE Auxiliary 587 Injection Pump 42 Heat Exchanger Cooling Water Room North Safety North Safety Injection Pump Mech Seal Component 2-HE-34NW Auxiliary 587 Injection Pump 42 Heat Exchanger Cooling Water Room South Safety South Safety Injection Pump Mech Seal Component 2-HE-34SE Auxiliary 587 Injection Pump 43 Heat Exchanger Cooling Water Room South Safety South Safety Injection Pump Mech Seal Component 2-HE-34SW Auxiliary 587 Injection Pump 43 Heat Exchanger Cooling Water Room North Safety Component 2-HE-35N North Safety Injection Pump Oil Cooler Auxiliary 587 Injection Pump 42 Cooling Water Room Unit 2

UFSAR Revision 31.0 INDIANA MICHIGAN POWER Revised: 26.0 Table: 14.4.2-1 D. C. COOK NUCLEAR PLANT Part 2 of 5 UPDATED FINAL SAFETY ANALYSIS REPORT Page: 16 of 23 Equipment Required to Shutdown Reactor (Unit 2)

(For High Energy Pipe Ruptures Outside the Containment)

Equip Id Equipment Description System Building Elev Room Rm#

South Safety Component 2-HE-35S South Safety Injection Pump Oil Cooler Auxiliary 587 Injection Pump 43 Cooling Water Room East Centrifugal East Centrifugal Charging Pump Component 2-HE-37E Auxiliary 587 Charging Pump 40 Gear Oil Cooler Cooling Water Room West Centrifugal West Centrifugal Charging Pump Component 2-HE-37W Auxiliary 587 Charging Pump 41 Gear Oil Cooler Cooling Water Room East Centrifugal East Centrifugal Charging Pump Component 2-HE-38E Auxiliary 587 Charging Pump 40 Bearing Oil Cooler Cooling Water Room West Centrifugal West Centrifugal Charging Pump Component 2-HE-38W Auxiliary 587 Charging Pump 41 Bearing Oil Cooler Cooling Water Room AB Emergency Diesel Diesel 2-HE-47-ABN Auxiliary 587 AB EDG Room 121 North Combustion Air Aftercooler Combustion Air Unit 2

UFSAR Revision 31.0 INDIANA MICHIGAN POWER Revised: 26.0 Table: 14.4.2-1 D. C. COOK NUCLEAR PLANT Part 2 of 5 UPDATED FINAL SAFETY ANALYSIS REPORT Page: 17 of 23 Equipment Required to Shutdown Reactor (Unit 2)

(For High Energy Pipe Ruptures Outside the Containment)

Equip Id Equipment Description System Building Elev Room Rm#

AB Emergency Diesel Diesel 2-HE-47-ABS Auxiliary 587 AB EDG Room 121 South Combustion Air Aftercooler Combustion Air CD Emergency Diesel Diesel 2-HE-47-CDN Auxiliary 587 CD EDG Room 122 North Combustion Air Aftercooler Combustion Air CD Emergency Diesel Diesel 2-HE-47-CDS Auxiliary 587 CD EDG Room 122 South Combustion Air Aftercooler Combustion Air Control Room Air Conditioning Control Room Control Rm A/C 2-HE-63N North Liquid Chiller HV-ACR-1 Auxiliary 650 129 Ventilation Room Evaporator Control Room Air Conditioning South Control Room Control Rm A/C 2-HE-63S Auxiliary 650 129 Liquid Chiller HV-ACR-2 Evaporator Ventilation Room Control Room Air Conditioning North Control Room Control Rm A/C 2-HE-64N Auxiliary 650 129 Liquid Chiller HV-ACR-1 Condenser Ventilation Room Control Room Air Conditioning South Control Room Control Rm A/C 2-HE-64S Auxiliary 650 129 Liquid Chiller HV-ACR-2 Condenser Ventilation Room Unit 2

UFSAR Revision 31.0 INDIANA MICHIGAN POWER Revised: 26.0 Table: 14.4.2-1 D. C. COOK NUCLEAR PLANT Part 2 of 5 UPDATED FINAL SAFETY ANALYSIS REPORT Page: 18 of 23 Equipment Required to Shutdown Reactor (Unit 2)

(For High Energy Pipe Ruptures Outside the Containment)

Equip Id Equipment Description System Building Elev Room Rm#

Control Room Air Conditioning Control Room Control Rm A/C 2-HV-ACR-1 Auxiliary 650 129 North Liquid Chiller Ventilation Room Control Room Air Conditioning Control Room Control Rm A/C 2-HV-ACR-2 Auxiliary 650 129 South Liquid Chiller Ventilation Room Control Room Ventilation Control Room Control Rm A/C 2-HV-ACRA-1 Auxiliary 650 129 North Air Conditioning Unit Ventilation Room Control Room Ventilation Control Room Control Rm A/C 2-HV-ACRA-2 Auxiliary 650 129 South Air Conditioning Unit Ventilation Room Outside Air to Control Room Ventilation Control Room Control Rm A/C 2-HV-ACR-DA-1 Units HV-ACRA-1 and HV-ACRA-2 Vent Auxiliary 650 129 Ventilation Room Damper Control Room Ventilation Control Room Control Rm A/C 2-HV-ACR-DA-2 Auxiliary 650 129 Outside Air Intake Damper Ventilation Room Control Room Ventilation Control Room Control Rm A/C 2-HV-ACR-DA-3 Auxiliary 650 129 Return Air Damper Ventilation Room Unit 2

UFSAR Revision 31.0 INDIANA MICHIGAN POWER Revised: 26.0 Table: 14.4.2-1 D. C. COOK NUCLEAR PLANT Part 2 of 5 UPDATED FINAL SAFETY ANALYSIS REPORT Page: 19 of 23 Equipment Required to Shutdown Reactor (Unit 2)

(For High Energy Pipe Ruptures Outside the Containment)

Equip Id Equipment Description System Building Elev Room Rm#

Control Room Pressurizer/Cleanup Filter Control Room Control Rm A/C 2-HV-ACRF-1 Auxiliary 650 129 Supply Fan Ventilation Room Control Room Pressurizer/Cleanup Filter Control Room Control Rm A/C 2-HV-ACRF-2 Auxiliary 650 129 Supply Fan Ventilation Room Auxiliary Normal Auxiliary Building Ventilation Engineered 2-HV-AES-1 Building Auxiliary 633 Blowdown 8 Safety Feature Exhaust - Unit 1 Ventilation Flashtank Room Auxiliary Normal Auxiliary Building Ventilation Engineered 2-HV-AES-1 (FLT) Building Auxiliary 633 Blowdown 8 Safety Feature Exhaust Air Filter Ventilation Flashtank Room Auxiliary Building Ventilation Engineered Auxiliary Normal 2-HV-AES-1D1 Safety Feature Exhaust Unit HV-AES-1 Building Auxiliary 633 Blowdown 8 Charcoal Filter Bypass Damper #1 Ventilation Flashtank Room Auxiliary Building Ventilation Engineered Auxiliary Normal 2-HV-AES-1D2 Safety Feature Exhaust Unit HV-AES-1 Building Auxiliary 633 Blowdown 8 Charcoal Filter Bypass Damper #2 Ventilation Flashtank Room Unit 2

UFSAR Revision 31.0 INDIANA MICHIGAN POWER Revised: 26.0 Table: 14.4.2-1 D. C. COOK NUCLEAR PLANT Part 2 of 5 UPDATED FINAL SAFETY ANALYSIS REPORT Page: 20 of 23 Equipment Required to Shutdown Reactor (Unit 2)

(For High Energy Pipe Ruptures Outside the Containment)

Equip Id Equipment Description System Building Elev Room Rm#

Aux Building Ventilation Engineered Auxiliary Normal 2-HV-AES-1D3 Safety Feature Exhaust Unit HV-AES-1 Building Auxiliary 633 Blowdown 8 Charcoal Filter Face Damper Ventilation Flashtank Room Auxiliary Normal Auxiliary Building Ventilation Engineered 2-HV-AES-2 Building Auxiliary 633 Blowdown 8 Safety Feature Exhaust Unit Ventilation Flashtank Room Auxiliary Normal Auxiliary Building Ventilation Engineered 2-HV-AES-2 (FLT) Building Auxiliary 633 Blowdown 8 Safety Feature Exhaust Air Filter Ventilation Flashtank Room Aux Building Ventilation Engineered Auxiliary Normal 2-HV-AES-2D1 Safety Feature Exhaust Unit HV-AES-2 Building Auxiliary 633 Blowdown 8 Charcoal Filter Bypass Damper #1 Ventilation Flashtank Room Aux Building Ventilation Safety Feature Auxiliary Normal 2-HV-AES-2D2 Exhaust Unit HV-AES-2 Charcoal Filter Building Auxiliary 633 Blowdown 8 Bypass Damper #2 Ventilation Flashtank Room Unit 2

UFSAR Revision 31.0 INDIANA MICHIGAN POWER Revised: 26.0 Table: 14.4.2-1 D. C. COOK NUCLEAR PLANT Part 2 of 5 UPDATED FINAL SAFETY ANALYSIS REPORT Page: 21 of 23 Equipment Required to Shutdown Reactor (Unit 2)

(For High Energy Pipe Ruptures Outside the Containment)

Equip Id Equipment Description System Building Elev Room Rm#

Aux Building Ventilation Engineered Auxiliary Normal 2-HV-AES-2D3 Safety Feature Exhaust Unit HV-AES-2 Building Auxiliary 633 Blowdown 8 Charcoal Filter Face Damper Ventilation Flashtank Room Plant Battery Train 'N' Train 'N' Battery Room AFW Battery 2-HV-AFP-BRE-1 Auxiliary 633 Auxiliary 263 East Exhaust Fan Rm Ventilation Equipment Room Auxiliary Normal Train 'N' Battery Room 2-HV-AFP-BRE-2 Building Auxiliary 633 Blowdown 8 West Exhaust Fan Ventilation Flashtank Room Turbine East Motor Driven East MDAFP 2-HV-AFP-EAC Building Turbine 591 50 Auxiliary Feedwater Pump Room Cooler Room Ventilation Turbine Turbine Driven Auxiliary 2-HV-AFP-T1AC Building Turbine 591 TDAFP Room 49 Feedwater Pump Room Cooler Ventilation Unit 2

UFSAR Revision 31.0 INDIANA MICHIGAN POWER Revised: 26.0 Table: 14.4.2-1 D. C. COOK NUCLEAR PLANT Part 2 of 5 UPDATED FINAL SAFETY ANALYSIS REPORT Page: 22 of 23 Equipment Required to Shutdown Reactor (Unit 2)

(For High Energy Pipe Ruptures Outside the Containment)

Equip Id Equipment Description System Building Elev Room Rm#

Turbine Turbine Driven Auxiliary 2-HV-AFP-T2AC Building Turbine 591 TDAFP Room 49 Feedwater Pump Room Cooler Ventilation Turbine West Motor Driven West MDAFP 2-HV-AFP-WAC Building Turbine 591 51 Auxiliary Feedwater Pump Room Cooler Room Ventilation Emergency AB Emergency Diesel Diesel Generator 2-HV-DDP-AB1 Generator Room Ventilation Exhaust Fan Auxiliary 587 AB EDG Room 121 Room HV-DGX-2 Tempering Air Damper Ventilation Emergency AB Emergency Diesel Diesel Generator 2-HV-DDP-AB2 Generator Room Ventilation Supply Fan Auxiliary 587 AB EDG Room 121 Room HV-DGS-2 Tempering Air Damper Ventilation Emergency CD Emergency Diesel Diesel Generator 2-HV-DDP-CD1 Generator Room Ventilation Exhaust Fan Auxiliary 587 CD EDG Room 122 Room HV-DGX-1 Tempering Air Damper Ventilation Unit 2

UFSAR Revision 31.0 INDIANA MICHIGAN POWER Revised: 26.0 Table: 14.4.2-1 D. C. COOK NUCLEAR PLANT Part 2 of 5 UPDATED FINAL SAFETY ANALYSIS REPORT Page: 23 of 23 Equipment Required to Shutdown Reactor (Unit 2)

(For High Energy Pipe Ruptures Outside the Containment)

Equip Id Equipment Description System Building Elev Room Rm#

CD Emergency Diesel Diesel Room 2-HV-DDP-CD2 Generator Room Ventilation Supply Fan Auxiliary 587 CD EDG Room 122 Ventilation HV-DGS-1 Tempering Air Damper CD Emergency Diesel Diesel Room 2-HV-DGS-1 Auxiliary 587 CD EDG Room 122 Generator Room Ventilation Supply Fan Ventilation AB Emergency Diesel Diesel Room 2-HV-DGS-2 Auxiliary 587 AB EDG Room 121 Generator Room Ventilation Supply Fan Ventilation AB Emergency Diesel Diesel Room 2-HV-DGS-3 Generator Room Cabinet Ventilation Auxiliary 587 AB EDG Room 121 Ventilation Supply Fan CD Emergency Diesel Diesel Room 2-HV-DGS-4 Generator Room Cabinet Ventilation Auxiliary 587 CD EDG Room 122 Ventilation Supply Fan Unit 2

UFSAR Revision 31.0 INDIANA MICHIGAN POWER Revised: 26.0 Table: 14.4.2-1 D. C. COOK NUCLEAR PLANT Part 3 of 5 UPDATED FINAL SAFETY ANALYSIS REPORT Page: 1 of 26 Equipment Required to Shutdown Reactor (Unit 2)

(For High Energy Pipe Ruptures Outside the Containment)

Equip Id Equipment Description System Building Elev Room Rm#

AB Emergency Diesel Diesel Room Inner Plant 2-HV-DGS-DAB Generator Room Ventilation Supply Fan Auxiliary 609 244 Ventilation Grounds HV-DGS-1 Outside Air Shutoff Damper Emergency CD Emergency Diesel Diesel Generator Reactor Cable 2-HV-DGS-DCD Generator Room Ventilation Supply Fan Auxiliary 596 26 Room Tunnel Quad #3 HV-DGS-2 Outside Air Shutoff Damper Ventilation Emergency CD Emergency Diesel Diesel Generator 2-HV-DGX-1 Auxiliary 587 CD EDG Room 122 Generator Room Ventilation Exhaust Fan Room Ventilation Emergency AB Emergency Diesel Diesel Generator 2-HV-DGX-2 Auxiliary 587 AB EDG Room 121 Generator Room Ventilation Exhaust Fan Room Ventilation Control Rod Drive Equipment Room and 4kv Room -

ELEC. SWGR.

2-HV-SGR-MD-1 Inverter Area Ventilation Recirculating Air Auxiliary 609 600v Switchgear 204 Ventilation Inlet Damper Area Unit 2

UFSAR Revision 31.0 INDIANA MICHIGAN POWER Revised: 26.0 Table: 14.4.2-1 D. C. COOK NUCLEAR PLANT Part 3 of 5 UPDATED FINAL SAFETY ANALYSIS REPORT Page: 2 of 26 Equipment Required to Shutdown Reactor (Unit 2)

(For High Energy Pipe Ruptures Outside the Containment)

Equip Id Equipment Description System Building Elev Room Rm#

Control Rod Drive Equipment Room and 4kv Room -

ELEC. SWGR.

2-HV-SGR-MD-2 Inverter Area Ventilation Auxiliary 609 600v Switchgear 204 Ventilation Outside Air Inlet Damper Area 4kv Rm 600 Volt Switchgear Xformers 4kv Room -

ELEC. SWGR.

2-HV-SGR-MD-3 TR21A & TR21C Area Vent Supply Fan Auxiliary 609 600v Switchgear 204 Ventilation HV-SGRS-8 Suction Damper Area 4kv Room 600v Switchgear Transformers 4kv Room -

ELEC. SWGR.

2-HV-SGR-MD-4 Area Ventilation Supply Fan HV-SGRS-7 Auxiliary 609 600v Switchgear 204 Ventilation Suction Damper Area 600Vac Motor Control Center Mezzanine ELEC. SWGR. 4kv Room -

2-HV-SGR-MD-5 Area Ventilation Supply Fan HV-SGRS-9 Auxiliary 613 205 Ventilation Mezzanine Area Vent Damper Control Rod Drive Equipment Room and 4kv Room -

ELEC. SWGR.

2-HV-SGRS-1A Inverter Area Ventilation North Supply Auxiliary 609 600v Switchgear 204 Ventilation Fan Area 4kv Room - AB 4kv Room AB 4kv Switchgear Area ELEC. SWGR.

2-HV-SGRS-2 Auxiliary 609 4kv Switchgear 140 Ventilation Supply Fan Ventilation Area Unit 2

UFSAR Revision 31.0 INDIANA MICHIGAN POWER Revised: 26.0 Table: 14.4.2-1 D. C. COOK NUCLEAR PLANT Part 3 of 5 UPDATED FINAL SAFETY ANALYSIS REPORT Page: 3 of 26 Equipment Required to Shutdown Reactor (Unit 2)

(For High Energy Pipe Ruptures Outside the Containment)

Equip Id Equipment Description System Building Elev Room Rm#

4kv Room - CD 4kv Room CD 4kv Switchgear Area ELEC. SWGR.

2-HV-SGRS-3 Auxiliary 609 4kv Switchgear 206 Ventilation Supply Fan Ventilation Area Control Rod Drive Equipment Room and 4kv Room -

ELEC. SWGR.

2-HV-SGRS-4A Inverter Area Ventilation South Supply Auxiliary 609 600v Switchgear 204 Ventilation Fan Area 4kv Room 600 Volt Switchgear 4kv Room -

ELEC. SWGR.

2-HV-SGRS-7 Transformers TR21B and TR21D Area Auxiliary 609 600v Switchgear 204 Ventilation Ventilation Supply Fan Area 4kv Room 600 Volt Switchgear 4kv Room -

ELEC. SWGR.

2-HV-SGRS-8 Transformers TR21A and TR21C Area Auxiliary 609 600v Switchgear 204 Ventilation Ventilation Supply Fan Area 600Vac Motor Control Center Mezzanine ELEC. SWGR. 4kv Room -

2-HV-SGRS-9 Auxiliary 613 205 Area Ventilation Supply Fan Ventilation Mezzanine Area 4kv Room - AB 4kv Room AB 4kv Switchgear Area ELEC. SWGR.

2-HV-SGRX-2 Auxiliary 609 4kv Switchgear 140 Ventilation Exhaust Fan Ventilation Area Unit 2

UFSAR Revision 31.0 INDIANA MICHIGAN POWER Revised: 26.0 Table: 14.4.2-1 D. C. COOK NUCLEAR PLANT Part 3 of 5 UPDATED FINAL SAFETY ANALYSIS REPORT Page: 4 of 26 Equipment Required to Shutdown Reactor (Unit 2)

(For High Energy Pipe Ruptures Outside the Containment)

Equip Id Equipment Description System Building Elev Room Rm#

4kv Room - CD 4kv Room CD 4kv Switchgear Area ELEC. SWGR.

2-HV-SGRX-3 Auxiliary 609 4kv Switchgear 206 Ventilation Exhaust Fan Ventilation Area AB Battery Equipment Area ELEC. SWGR. AB BATT Equip 2-HV-SGRX-5 Auxiliary 609 200 Battery Room Ventilation Exhaust Fan Ventilation Area CD Battery Equipment Area ELEC. SWGR. CD BATT Equip 2-HV-SGRX-6 Auxiliary 626 201 Battery Room Ventilation Exhaust Fan Ventilation Area RHR to Reactor Coolant Loops #2 & #3 Residual Heat Annulus -

2-ICM-111 Containment 598 59 Cold Legs Containment Isolation Valve Removal Quadrant #2 Reactor Coolant Loop #2 Hot Leg to Residual Heat Annulus -

2-ICM-129 Residual Heat Removal Pumps Suction Containment 598 59 Removal Quadrant #2 Containment Isolation Valve Boron Injection Tank Train 'A' Outlet BIT Outlet 2-ICM-250 Boron Injection Auxiliary 612 15 Containment Isolation Valve Valve Room Boron Injection Tank Train 'B' Outlet BIT Outlet 2-ICM-251 Boron Injection Auxiliary 612 15 Containment Isolation Valve Valve Room Unit 2

UFSAR Revision 31.0 INDIANA MICHIGAN POWER Revised: 26.0 Table: 14.4.2-1 D. C. COOK NUCLEAR PLANT Part 3 of 5 UPDATED FINAL SAFETY ANALYSIS REPORT Page: 5 of 26 Equipment Required to Shutdown Reactor (Unit 2)

(For High Energy Pipe Ruptures Outside the Containment)

Equip Id Equipment Description System Building Elev Room Rm#

North Safety North Safety Injection Pump PP-26N 2-ICM-260 Safety Injection Auxiliary 587 Injection Pump 42 Discharge Containment Isolation Valve Room South Safety South Safety Injection Pump PP-26S 2-ICM-265 Safety Injection Auxiliary 587 Injection Pump 43 Discharge Containment Isolation Valve Room Recirculation Sump to East RHR/CTS Residual Heat 2-ICM-305 Pumps Suction Containment Isolation Auxiliary 591 Vestibule 28 Removal Valve Recirculation Sump to West RHR/CTS Residual Heat 2-ICM-306 Pumps Suction Containment Isolation Auxiliary 591 Vestibule 28 Removal Valve East Residual Heat Removal to RC Loops East RHR Heat Residual Heat 2-ICM-311 #1 and #4 Cold Legs Containment Auxiliary 609 Exchanger 5 Removal Isolation Valve Room West RHR to Reactor Coolant Loops #2 West RHR Heat Residual Heat 2-ICM-321 and #3 Cold Legs Containment Isolation Auxiliary 609 Exchanger 6 Removal Valve Room Unit 2

UFSAR Revision 31.0 INDIANA MICHIGAN POWER Revised: 26.0 Table: 14.4.2-1 D. C. COOK NUCLEAR PLANT Part 3 of 5 UPDATED FINAL SAFETY ANALYSIS REPORT Page: 6 of 26 Equipment Required to Shutdown Reactor (Unit 2)

(For High Energy Pipe Ruptures Outside the Containment)

Equip Id Equipment Description System Building Elev Room Rm#

East Residual Heat Removal Pump PP-35E Residual Heat 2-IFC-315 Auxiliary 573 573 Hallway 573 Discharge Flow Switch Removal West Residual Heat Removal Pump PP- Residual Heat 2-IFC-325 Auxiliary 573 573 Hallway 573 35W Discharge Flow Switch Removal North Safety Safety Injection Pump 2-IFI-260 Safety Injection Auxiliary 587 Injection Pump 42 Discharge Flow Indicator Room South Safety Safety Injection Pump 2-IFI-266 Safety Injection Auxiliary 587 Injection Pump 43 Discharge Flow Indicator Room East Residual Heat Removal Heat Residual Heat 2-IFI-310 Exchanger HE-17E Outlet Low Range Auxiliary 609 609 Hallway 609 Removal Flow Indicator Transmitter East Residual Heat Removal Heat Residual Heat 2-IFI-311 Exchanger HE-17E Outlet High Range Auxiliary 609 609 Hallway 609 Removal Flow Indicator Transmitter Unit 2

UFSAR Revision 31.0 INDIANA MICHIGAN POWER Revised: 26.0 Table: 14.4.2-1 D. C. COOK NUCLEAR PLANT Part 3 of 5 UPDATED FINAL SAFETY ANALYSIS REPORT Page: 7 of 26 Equipment Required to Shutdown Reactor (Unit 2)

(For High Energy Pipe Ruptures Outside the Containment)

Equip Id Equipment Description System Building Elev Room Rm#

West Residual Heat Removal Heat Residual Heat 2-IFI-320 Exchanger HE-17W Outlet Low Range Auxiliary 609 609 Hallway 609 Removal Flow Indicator Transmitter West Residual Heat Removal Heat Residual Heat 2-IFI-321 Exchanger HE-17W Outlet High Range Auxiliary 609 609 Hallway 609 Removal Flow Indicator Transmitter Residual Heat Removal to Reactor Coolant Residual Heat 2-IFI-335 Loops #2 and #3 Cold Legs Flow Indicator Auxiliary 591 Vestibule 28 Removal Transmitter Boron Injection to Reactor Coolant Loop Annulus -

2-IFI-51 Boron Injection Containment 598 58

1 Flow Indicator Transmitter Quadrant #1 Boron Injection to Reactor Coolant Loop Annulus -

2-IFI-52 Boron Injection Containment 598 59

2 Flow Indicator Transmitter Quadrant #2 Boron Injection to Reactor Coolant Loop Annulus -

2-IFI-53 Boron Injection Containment 598 56

3 Flow Indicator Transmitter Quadrant #3 Boron Injection to Reactor Coolant Loop Annulus -

2-IFI-54 Boron Injection Containment 598 57

4 Flow Indicator Transmitter Quadrant #4 Unit 2

UFSAR Revision 31.0 INDIANA MICHIGAN POWER Revised: 26.0 Table: 14.4.2-1 D. C. COOK NUCLEAR PLANT Part 3 of 5 UPDATED FINAL SAFETY ANALYSIS REPORT Page: 8 of 26 Equipment Required to Shutdown Reactor (Unit 2)

(For High Energy Pipe Ruptures Outside the Containment)

Equip Id Equipment Description System Building Elev Room Rm#

Reactor Coolant Loop #2 Hot Leg to Lower Residual Heat 2-IMO-128 Residual Heat Removal Pumps Suction Containment 617 Containment, 61 Removal Shutoff Valve Quadrant #2 East RWST to East Containment Spray Pump Containment Containment 2-IMO-215 PP-9E Suction Motor Operated Shut-Off Auxiliary 573 53 Spray Spray Pump Valve Room West RWST to West Containment Spray Pump Containment Containment 2-IMO-225 PP-9W Suction Motor Operated Shut-Off Auxiliary 573 52 Spray Spray Pump Valve Room Boron Injection Tank 2-IMO-255 Boron Injection Auxiliary 612 BIT Room 16 Train 'A' Inlet Shutoff Valve Boron Injection Tank 2-IMO-256 Boron Injection Auxiliary 612 BIT Room 16 Train 'B' Inlet Shutoff Valve Refueling Water Storage Tank TK-33 South Safety 2-IMO-261 Supply to Safety Injection Pumps Shutoff Safety Injection Auxiliary 587 Injection Pump 43 Valve Room Unit 2

UFSAR Revision 31.0 INDIANA MICHIGAN POWER Revised: 26.0 Table: 14.4.2-1 D. C. COOK NUCLEAR PLANT Part 3 of 5 UPDATED FINAL SAFETY ANALYSIS REPORT Page: 9 of 26 Equipment Required to Shutdown Reactor (Unit 2)

(For High Energy Pipe Ruptures Outside the Containment)

Equip Id Equipment Description System Building Elev Room Rm#

Safety Injection Pumps Recirc to North Safety 2-IMO-262 Refueling Water Storage Tank TK-33 Safety Injection Auxiliary 587 Injection Pump 42 Train 'A' Shutoff Valve Room Safety Injection Pumps Recirc to North Safety 2-IMO-263 Refueling Water Storage Tank TK-33 Safety Injection Auxiliary 587 Injection Pump 42 Train 'B' Shutoff Valve Room North Safety Safety Injection Pumps Discharge Crosstie 2-IMO-270 Safety Injection Auxiliary 587 Injection Pump 42 Train 'A' Shutoff Valve Room South Safety Safety Injection Pumps Discharge Crosstie 2-IMO-275 Safety Injection Auxiliary 587 Injection Pump 43 Train 'B' Shutoff Valve Room East Residual Heat Removal Pump PP-35E Residual Heat East RHR Pump 2-IMO-310 Auxiliary 573 54 Suction Shutoff Valve Removal Room East Residual Heat Removal Heat East RHR Heat Residual Heat 2-IMO-312 Exchanger HE-17E Outlet Mini-Flow Line Auxiliary 609 Exchanger 5 Removal Shutoff Valve Room Unit 2

UFSAR Revision 31.0 INDIANA MICHIGAN POWER Revised: 26.0 Table: 14.4.2-1 D. C. COOK NUCLEAR PLANT Part 3 of 5 UPDATED FINAL SAFETY ANALYSIS REPORT Page: 10 of 26 Equipment Required to Shutdown Reactor (Unit 2)

(For High Energy Pipe Ruptures Outside the Containment)

Equip Id Equipment Description System Building Elev Room Rm#

East Residual Heat Removal Heat East RHR Heat Residual Heat 2-IMO-314 Exchanger 2-HE-17E to RC Loops #2 and Auxiliary 609 Exchanger 5 Removal

3 Cold Legs Shutoff Valve Room East East RHR and North Safety Injection to Residual Heat Containment 2-IMO-315 Reactor Coolant Loops #1 and #4 Hot Containment 612 72 Removal Lower Vent Legs Shutoff Valve Room East East RHR and North Safety Injection to Residual Heat Containment 2-IMO-316 Reactor Coolant Loops #1 and #4 Cold Containment 612 72 Removal Lower Vent Legs Shutoff Valve Room West Residual Heat Removal Pump PP- Residual Heat West RHR 2-IMO-320 Auxiliary 573 55 35W Suction Shutoff Valve Removal Pump Room West Residual Heat Removal Heat West RHR Heat Residual Heat 2-IMO-322 Exchanger HE-17W Outlet Mini-Flow Auxiliary 609 Exchanger 6 Removal Line Shutoff Valve Room Unit 2

UFSAR Revision 31.0 INDIANA MICHIGAN POWER Revised: 26.0 Table: 14.4.2-1 D. C. COOK NUCLEAR PLANT Part 3 of 5 UPDATED FINAL SAFETY ANALYSIS REPORT Page: 11 of 26 Equipment Required to Shutdown Reactor (Unit 2)

(For High Energy Pipe Ruptures Outside the Containment)

Equip Id Equipment Description System Building Elev Room Rm#

West Residual Heat Removal Heat West RHR Heat Residual Heat 2-IMO-324 Exchanger 2-HE-17W to RC Loops #2 and Auxiliary 609 Exchanger 6 Removal

3 Cold Legs Shutoff Valve Room West West RHR and South Safety Injection to Residual Heat Containment 2-IMO-325 Reactor Coolant Loops #2 and #3 Hot Containment 612 73 Removal Lower Vent Legs Shutoff Valve Room West West RHR and South Safety Injection to Residual Heat Containment 2-IMO-326 Reactor Coolant Loops #2 and #3 Cold Containment 612 73 Removal Lower Vent Legs Shutoff Valve Room East RHR Heat East Residual Heat Removal to Upper Residual Heat 2-IMO-330 Auxiliary 609 Exchanger 5 Containment Spray Shutoff Valve Removal Room West RHR Heat West RHR to Upper Containment Spray Residual Heat 2-IMO-331 Auxiliary 609 Exchanger 6 Shutoff Valve Removal Room Unit 2

UFSAR Revision 31.0 INDIANA MICHIGAN POWER Revised: 26.0 Table: 14.4.2-1 D. C. COOK NUCLEAR PLANT Part 3 of 5 UPDATED FINAL SAFETY ANALYSIS REPORT Page: 12 of 26 Equipment Required to Shutdown Reactor (Unit 2)

(For High Energy Pipe Ruptures Outside the Containment)

Equip Id Equipment Description System Building Elev Room Rm#

East Residual Heat Removal Heat East RHR Heat Residual Heat 2-IMO-340 Exchanger to Charging Pumps Suction Auxiliary 609 Exchanger 5 Removal Shutoff Valve Room West RHR Heat Exchanger Outlet to West RHR Heat Residual Heat 2-IMO-350 Safety Injection Pump Suction Shutoff Auxiliary 609 Exchanger 6 Removal Valve Room Safety Injection Pumps to CVCS Charging West Centrifugal (CVCS) 2-IMO-360 Pumps Suction Header Crosstie Shutoff Auxiliary 587 Charging Pump 41 Charging Valve Room Safety Injection Pumps Suction to and North Safety 2-IMO-361 From Charging Pumps Suction Train 'A' Safety Injection Auxiliary 587 Injection Pump 42 Shutoff Valve Room Safety Injection Pumps Suction to and North Safety 2-IMO-362 From Charging Pumps Suction Train 'B' Safety Injection Auxiliary 587 Injection Pump 42 Shutoff Valve Room Refueling Water Storage Tank TK-33 to Residual Heat 2-IMO-390 Residual Heat Removal Pumps Suction Auxiliary 591 Vestibule 28 Removal Shutoff Valve Unit 2

UFSAR Revision 31.0 INDIANA MICHIGAN POWER Revised: 26.0 Table: 14.4.2-1 D. C. COOK NUCLEAR PLANT Part 3 of 5 UPDATED FINAL SAFETY ANALYSIS REPORT Page: 13 of 26 Equipment Required to Shutdown Reactor (Unit 2)

(For High Energy Pipe Ruptures Outside the Containment)

Equip Id Equipment Description System Building Elev Room Rm#

Boron Injection to Reactor Coolant Loop Annulus -

2-IMO-51 Boron Injection Containment 598 58

1 Shutoff Valve Quadrant #1 Boron Injection to Reactor Coolant Loop Annulus -

2-IMO-52 Boron Injection Containment 598 59

2 Shutoff Valve Quadrant #2 Boron Injection to Reactor Coolant Loop Annulus -

2-IMO-53 Boron Injection Containment 598 56

3 Shutoff Valve Quadrant #3 Boron Injection to Reactor Coolant Loop Annulus -

2-IMO-54 Boron Injection Containment 598 57

4 Shutoff Valve Quadrant #4 Refueling Water Storage Tank to CVCS Reciprocating (CVCS) 2-IMO-910 Charging Pumps Suction Header Train 'A' Auxiliary 587 Charging Pump 39 Charging Shutoff Valve Room Refueling Water Storage Tank to CVCS East Centrifugal (CVCS) 2-IMO-911 Charging Pumps Suction Header Train 'B' Auxiliary 587 Charging Pump 40 Charging Shutoff Valve Room East Residual Heat Removal Heat East RHR Heat Residual Heat 2-IRV-310 Exchanger HE-17E 8" Air Operated Outlet Auxiliary 609 Exchanger 5 Removal Flow Control Valve Room Unit 2

UFSAR Revision 31.0 INDIANA MICHIGAN POWER Revised: 26.0 Table: 14.4.2-1 D. C. COOK NUCLEAR PLANT Part 3 of 5 UPDATED FINAL SAFETY ANALYSIS REPORT Page: 14 of 26 Equipment Required to Shutdown Reactor (Unit 2)

(For High Energy Pipe Ruptures Outside the Containment)

Equip Id Equipment Description System Building Elev Room Rm#

Residual Heat Removal Heat Exchangers East RHR Heat Residual Heat 2-IRV-311 Bypass Flow 8" Air Operated Control Auxiliary 609 Exchanger 5 Removal Valve Room West Residual Heat Removal Heat West RHR Heat Residual Heat 2-IRV-320 Exchanger HE-17W 8" Air Operated Auxiliary 609 Exchanger 6 Removal Outlet Flow Control Valve Room Safety Injection to Accumulator Fill Line Annulus -

2-IRV-60 Safety Injection Containment 598 59 Control Valve Quadrant #2 Residual Heat Removal to Reactor Coolant Residual Heat 2-ITR-335 Loops #2 & #3 Cold Legs Temperature Auxiliary 591 Vestibule 28 Removal Recorder Thermal Sensor AB Emergency Diesel 2-LLS-120 Fuel Oil Day Tank QT-107-AB High Diesel Fuel Oil Auxiliary 587 AB EDG Room 121 Level Switch #1 AB Emergency Diesel 2-LLS-121 Fuel Oil Day Tank QT-107-AB Low Diesel Fuel Oil Auxiliary 587 AB EDG Room 121 Level Switch #1 Unit 2

UFSAR Revision 31.0 INDIANA MICHIGAN POWER Revised: 26.0 Table: 14.4.2-1 D. C. COOK NUCLEAR PLANT Part 3 of 5 UPDATED FINAL SAFETY ANALYSIS REPORT Page: 15 of 26 Equipment Required to Shutdown Reactor (Unit 2)

(For High Energy Pipe Ruptures Outside the Containment)

Equip Id Equipment Description System Building Elev Room Rm#

AB Emergency Diesel 2-LLS-122 Fuel Oil Day Tank QT-107-AB High Diesel Fuel Oil Auxiliary 587 AB EDG Room 121 Level Switch #2 AB Emergency Diesel 2-LLS-123 Fuel Oil Day Tank QT-107-AB Low Diesel Fuel Oil Auxiliary 587 AB EDG Room 121 Level Switch #2 CD Emergency Diesel 2-LLS-125 Fuel Oil Day Tank QT-107-CD Diesel Fuel Oil Auxiliary 587 CD EDG Room 122 High Level Switch #1 CD Emergency Diesel 2-LLS-126 Fuel Oil Day Tank QT-107-CD Diesel Fuel Oil Auxiliary 587 CD EDG Room 122 Low Level Switch #1 CD Emergency Diesel 2-LLS-127 Fuel Oil Day Tank QT-107-CD Diesel Fuel Oil Auxiliary 587 CD EDG Room 122 High Level Switch #2 CD Emergency Diesel 2-LLS-128 Fuel Oil Day Tank QT-107-CD Diesel Fuel Oil Auxiliary 587 CD EDG Room 122 Low Level Switch #2 Unit 2

UFSAR Revision 31.0 INDIANA MICHIGAN POWER Revised: 26.0 Table: 14.4.2-1 D. C. COOK NUCLEAR PLANT Part 3 of 5 UPDATED FINAL SAFETY ANALYSIS REPORT Page: 16 of 26 Equipment Required to Shutdown Reactor (Unit 2)

(For High Energy Pipe Ruptures Outside the Containment)

Equip Id Equipment Description System Building Elev Room Rm#

AB Emergency Diesel 2-LRV-240 Diesel Lube Oil Auxiliary 587 AB EDG Room 121 Upper Valve Gear Lube Oil Regulator #1 AB Emergency Diesel 2-LRV-241 Diesel Lube Oil Auxiliary 587 AB EDG Room 121 Upper Valve Gear Lube Oil Regulator #2 CD Emergency Diesel 2-LRV-245 Upper Valve Gear Oil Pressure Regulating Diesel Lube Oil Auxiliary 587 CD EDG Room 122 Valve #1 CD Emergency Diesel 2-LRV-246 Diesel Lube Oil Auxiliary 587 CD EDG Room 122 Upper Valve Gear Lube Oil Regulator #2 AB Emergency Diesel 2-LSO-240 Upper Valve Gear Lubrication Control Diesel Lube Oil Auxiliary 587 AB EDG Room 121 Solenoid #1 AB Emergency Diesel Upper Valve Gear 2-LSO-241 Diesel Lube Oil Auxiliary 587 AB EDG Room 121 Lubrication Control Solenoid #2 CD Emergency Diesel 2-LSO-245 Gen Upper Valve Gear Lubrication Diesel Lube Oil Auxiliary 587 CD EDG Room 122 Control Solenoid #1 Unit 2

UFSAR Revision 31.0 INDIANA MICHIGAN POWER Revised: 26.0 Table: 14.4.2-1 D. C. COOK NUCLEAR PLANT Part 3 of 5 UPDATED FINAL SAFETY ANALYSIS REPORT Page: 17 of 26 Equipment Required to Shutdown Reactor (Unit 2)

(For High Energy Pipe Ruptures Outside the Containment)

Equip Id Equipment Description System Building Elev Room Rm#

CD Emergency Diesel 2-LSO-246 Gen Upper Valve Gear Lubrication Diesel Lube Oil Auxiliary 587 CD EDG Room 122 Control Solenoid #2 AB BATT Equip 2-MCAB 250Vdc Distribution Panel MCAB 250Vdc Auxiliary 609 200 Area CD BATT Equip 2-MCCD 250Vdc Distribution Panel MCCD 250Vdc Auxiliary 626 201 Area Main Steam Lead #2 to Auxiliary Feed West Main 2-MCM-221 Pump Turbine 4" Motor Operated Shutoff Main Steam Auxiliary 633 Steam Stop 9 Valve Enclosure Main Steam Lead #3 to Auxiliary Feed West Main 2-MCM-231 Pump Turbine 4" Motor Operated Shutoff Main Steam Auxiliary 633 Steam Stop 9 Valve Enclosure AB BATT Equip 2-MDAB 250Vdc Distribution Panel MDAB 250Vdc Auxiliary 609 200 Area CD BATT Equip 2-MDCD 250Vdc Distribution Panel MDCD 250Vdc Auxiliary 626 201 Area Unit 2

UFSAR Revision 31.0 INDIANA MICHIGAN POWER Revised: 26.0 Table: 14.4.2-1 D. C. COOK NUCLEAR PLANT Part 3 of 5 UPDATED FINAL SAFETY ANALYSIS REPORT Page: 18 of 26 Equipment Required to Shutdown Reactor (Unit 2)

(For High Energy Pipe Ruptures Outside the Containment)

Equip Id Equipment Description System Building Elev Room Rm#

Steam Generator OME-3-1 Annulus -

2-MFC-110 Main Steam Containment 598 58 Channel I Steam Flow Control Transmitter Quadrant #1 Steam Generator OME-3-1 Annulus -

2-MFC-111 Channel II Steam Flow Control Main Steam Containment 598 58 Quadrant #1 Transmitter Steam Generator OME-3-2 Annulus -

2-MFC-120 Channel II Steam Flow Control Main Steam Containment 598 59 Quadrant #2 Transmitter Steam Generator OME-3-2 Annulus -

2-MFC-121 Main Steam Containment 598 59 Channel I Steam Flow Control Transmitter Quadrant #2 Steam Generator OME-3-3 Annulus -

2-MFC-130 Channel II Steam Flow Control Main Steam Containment 598 56 Quadrant #3 Transmitter Steam Generator OME-3-3 Annulus -

2-MFC-131 Main Steam Containment 598 56 Channel I Steam Flow Control Transmitter Quadrant #3 Steam Generator OME-3-4 Annulus -

2-MFC-140 Main Steam Containment 598 57 Channel I Steam Flow Control Transmitter Quadrant #4 Unit 2

UFSAR Revision 31.0 INDIANA MICHIGAN POWER Revised: 26.0 Table: 14.4.2-1 D. C. COOK NUCLEAR PLANT Part 3 of 5 UPDATED FINAL SAFETY ANALYSIS REPORT Page: 19 of 26 Equipment Required to Shutdown Reactor (Unit 2)

(For High Energy Pipe Ruptures Outside the Containment)

Equip Id Equipment Description System Building Elev Room Rm#

Steam Generator OME-3-4 Annulus -

2-MFC-141 Channel II Steam Flow Control Main Steam Containment 598 57 Quadrant #4 Transmitter Steam Stop Valve MRV-210 East Main Steam 2-MMO-210 Steam Cylinder Dump 4" Motor Operated Main Steam Auxiliary 633 10 Stop Enclosure Valves Selector Valve Steam Stop Valve MRV-220 West Main 2-MMO-220 Steam Cylinder Dump 4" Motor Operated Main Steam Auxiliary 633 Steam Stop 9 Valves Selector Valve Enclosure Steam Stop Valve MRV-230 West Main 2-MMO-230 Steam Cylinder Dump 4" Motor Operated Main Steam Auxiliary 633 Steam Stop 9 Valves Selector Valve Enclosure Steam Stop Valve MRV-240 East Main Steam 2-MMO-240 Steam Cylinder Dump 4" Motor Operated Main Steam Auxiliary 633 10 Stop Enclosure Valves Selector Valve Steam Generator OME-3-1 East Main Steam 2-MPP-210 Main Steam Auxiliary 633 10 Channel I Steam Pressure Transmitter Stop Enclosure Unit 2

UFSAR Revision 31.0 INDIANA MICHIGAN POWER Revised: 26.0 Table: 14.4.2-1 D. C. COOK NUCLEAR PLANT Part 3 of 5 UPDATED FINAL SAFETY ANALYSIS REPORT Page: 20 of 26 Equipment Required to Shutdown Reactor (Unit 2)

(For High Energy Pipe Ruptures Outside the Containment)

Equip Id Equipment Description System Building Elev Room Rm#

Steam Generator OME-3-1 East Main Steam 2-MPP-211 Main Steam Auxiliary 633 10 Channel II Steam Pressure Transmitter Stop Enclosure Steam Generator OME-3-1 East Main Steam 2-MPP-212 Channel IV Reactor Protection Input Main Steam Auxiliary 633 10 Stop Enclosure Steam Pressure Transmitter West Main Steam Generator OME-3-2 2-MPP-220 Main Steam Auxiliary 633 Steam Stop 9 Channel I Steam Pressure Transmitter Enclosure West Main Steam Generator OME-3-2 2-MPP-221 Main Steam Auxiliary 633 Steam Stop 9 Channel II Steam Pressure Transmitter Enclosure Steam Generator OME-3-2 West Main 2-MPP-222 Channel III Reactor Protection Input Main Steam Auxiliary 633 Steam Stop 9 Steam Pressure Transmitter Enclosure West Main Steam Generator OME-3-3 2-MPP-230 Main Steam Auxiliary 633 Steam Stop 9 Channel I Steam Pressure Transmitter Enclosure Unit 2

UFSAR Revision 31.0 INDIANA MICHIGAN POWER Revised: 26.0 Table: 14.4.2-1 D. C. COOK NUCLEAR PLANT Part 3 of 5 UPDATED FINAL SAFETY ANALYSIS REPORT Page: 21 of 26 Equipment Required to Shutdown Reactor (Unit 2)

(For High Energy Pipe Ruptures Outside the Containment)

Equip Id Equipment Description System Building Elev Room Rm#

West Main Steam Generator OME-3-3 2-MPP-231 Main Steam Auxiliary 633 Steam Stop 9 Channel II Steam Pressure Transmitter Enclosure Steam Generator OME-3-3 West Main 2-MPP-232 Channel III Reactor Protection Input Main Steam Auxiliary 633 Steam Stop 9 Steam Pressure Transmitter Enclosure Steam Generator OME-3-4 East Main Steam 2-MPP-240 Main Steam Auxiliary 633 10 Channel I Steam Pressure Transmitter Stop Enclosure Steam Generator OME-3-4 East Main Steam 2-MPP-241 Main Steam Auxiliary 633 10 Channel II Steam Pressure Transmitter Stop Enclosure Steam Generator OME-3-4 East Main Steam 2-MPP-242 Channel IV Reactor Protection Input Main Steam Auxiliary 633 10 Stop Enclosure Steam Pressure Transmitter Steam Generator OME-3-1 East Main Steam 2-MRV-210 Main Steam Auxiliary 633 10 Stop Valve Stop Enclosure Unit 2

UFSAR Revision 31.0 INDIANA MICHIGAN POWER Revised: 26.0 Table: 14.4.2-1 D. C. COOK NUCLEAR PLANT Part 3 of 5 UPDATED FINAL SAFETY ANALYSIS REPORT Page: 22 of 26 Equipment Required to Shutdown Reactor (Unit 2)

(For High Energy Pipe Ruptures Outside the Containment)

Equip Id Equipment Description System Building Elev Room Rm#

Steam Generator #1 East Main Steam 2-MRV-211 Stop Valve MRV-210 Steam Cylinder Main Steam Auxiliary 633 10 Stop Enclosure Train 'A' Dump Valve Steam Generator #1 East Main Steam 2-MRV-212 Stop Valve MRV-210 Steam Cylinder Main Steam Auxiliary 633 10 Stop Enclosure Train 'B' Dump Valve Steam Generator OME-3-1 East Main Steam 2-MRV-213 Main Steam Auxiliary 633 10 Power Operated Relief Valve Stop Enclosure West Main Steam Generator OME-3-2 2-MRV-220 Main Steam Auxiliary 633 Steam Stop 9 Stop Valve Enclosure Steam Generator #2 West Main 2-MRV-221 Stop Valve MRV-220 Steam Cylinder Main Steam Auxiliary 633 Steam Stop 9 Train 'A' Dump Valve Enclosure Steam Generator #2 West Main 2-MRV-222 Stop Valve MRV-220 Steam Cylinder Main Steam Auxiliary 633 Steam Stop 9 Train 'B' Dump Valve Enclosure Unit 2

UFSAR Revision 31.0 INDIANA MICHIGAN POWER Revised: 26.0 Table: 14.4.2-1 D. C. COOK NUCLEAR PLANT Part 3 of 5 UPDATED FINAL SAFETY ANALYSIS REPORT Page: 23 of 26 Equipment Required to Shutdown Reactor (Unit 2)

(For High Energy Pipe Ruptures Outside the Containment)

Equip Id Equipment Description System Building Elev Room Rm#

West Main Steam Generator OME-3-2 2-MRV-223 Main Steam Auxiliary 633 Steam Stop 9 Power Operated Relief Valve Enclosure West Main Steam Generator OME-3-3 2-MRV-230 Main Steam Auxiliary 633 Steam Stop 9 Stop Valve Enclosure Steam Generator #3 West Main 2-MRV-231 Stop Valve MRV-230 Steam Cylinder Main Steam Auxiliary 633 Steam Stop 9 Train 'A' Dump Valve Enclosure Steam Generator #3 West Main 2-MRV-232 Stop Valve MRV-230 Steam Cylinder Main Steam Auxiliary 633 Steam Stop 9 Train 'B' Dump Valve Enclosure West Main Steam Generator OME-3-3 2-MRV-233 Main Steam Auxiliary 633 Steam Stop 9 Power Operated Relief Valve Enclosure Steam Generator OME-3-4 East Main Steam 2-MRV-240 Main Steam Auxiliary 633 10 Stop Valve Stop Enclosure Unit 2

UFSAR Revision 31.0 INDIANA MICHIGAN POWER Revised: 26.0 Table: 14.4.2-1 D. C. COOK NUCLEAR PLANT Part 3 of 5 UPDATED FINAL SAFETY ANALYSIS REPORT Page: 24 of 26 Equipment Required to Shutdown Reactor (Unit 2)

(For High Energy Pipe Ruptures Outside the Containment)

Equip Id Equipment Description System Building Elev Room Rm#

Steam Generator #4 East Main Steam 2-MRV-241 Stop Valve MRV-240 Steam Cylinder Main Steam Auxiliary 633 10 Stop Enclosure Train 'A' Dump Valve Steam Generator #4 East Main Steam 2-MRV-242 Stop Valve MRV-240 Steam Cylinder Main Steam Auxiliary 633 10 Stop Enclosure Train 'B' Dump Valve Steam Generator OME-3-4 East Main Steam 2-MRV-243 Main Steam Auxiliary 633 10 Power Operated Relief Valve Stop Enclosure Equipment Nuclear Instrumentation System Protection Control and 2-NIS-I Auxiliary 633 Control Room 123 Channel I Control Panel Indication Stations Equipment Nuclear Instrumentation System Protection Control and 2-NIS-III Auxiliary 633 Control Room 123 Channel III Control Panel Indication Stations Pressurizer OME-4 Instrumentation 2-NLI-151 Reactor Coolant Containment 612 67 Level Indicator Transmitter Room Unit 2

UFSAR Revision 31.0 INDIANA MICHIGAN POWER Revised: 26.0 Table: 14.4.2-1 D. C. COOK NUCLEAR PLANT Part 3 of 5 UPDATED FINAL SAFETY ANALYSIS REPORT Page: 25 of 26 Equipment Required to Shutdown Reactor (Unit 2)

(For High Energy Pipe Ruptures Outside the Containment)

Equip Id Equipment Description System Building Elev Room Rm#

Pressurizer OME-4 Instrumentation 2-NLP-151 Reactor Coolant Containment 612 67 Protection Channel I Level Transmitter Room Pressurizer OME-4 Instrumentation 2-NLP-152 Reactor Coolant Containment 612 67 Protection Channel II Level Transmitter Room Pressurizer OME-4 Instrumentation 2-NLP-153 Reactor Coolant Containment 612 67 Protection Channel III Level Transmitter Room Pressurizer Relief Valve NRV-151 Pressurizer 2-NMO-151 Upstream 3" Motor Operated Shutoff Reactor Coolant Containment 650 Enclosure, 81 Valve Interior Pressurizer Relief Valve NRV-152 Pressurizer 2-NMO-152 Upstream 3" Motor Operated Shutoff Reactor Coolant Containment 650 Enclosure, 81 Valve Interior Pressurizer Relief Valve NRV-153 Pressurizer 2-NMO-153 Upstream 3" Motor Operated Shutoff Reactor Coolant Containment 650 Enclosure, 81 Valve Interior Pressurizer OME-4 Instrumentation 2-NPP-151 Reactor Coolant Containment 612 67 Protection Channel I Pressure Transmitter Room Unit 2

UFSAR Revision 31.0 INDIANA MICHIGAN POWER Revised: 26.0 Table: 14.4.2-1 D. C. COOK NUCLEAR PLANT Part 3 of 5 UPDATED FINAL SAFETY ANALYSIS REPORT Page: 26 of 26 Equipment Required to Shutdown Reactor (Unit 2)

(For High Energy Pipe Ruptures Outside the Containment)

Equip Id Equipment Description System Building Elev Room Rm#

Pressurizer OME-4 Instrumentation 2-NPP-152 Reactor Coolant Containment 612 67 Protection Channel II Pressure Transmitter Room Pressurizer OME-4 Instrumentation 2-NPP-153 Protection Channel III Pressure Reactor Coolant Containment 612 67 Room Transmitter West Reactor Coolant Loop #2 Containment 2-NPS-121 Reactor Coolant Containment 612 73 Hot Leg Wide Range Pressure Transmitter Lower Vent Room East Reactor Coolant Loop #1 Containment 2-NPS-122 Reactor Coolant Containment 612 72 Hot Leg Wide Range Pressure Transmitter Lower Vent Room Pressurizer OME-4 Instrumentation 2-NPS-153 Protection Channel IV Pressure Reactor Coolant Containment 612 67 Room Transmitter Unit 2

UFSAR Revision 31.0 INDIANA MICHIGAN POWER Revised: 26.0 Table: 14.4.2-1 D. C. COOK NUCLEAR PLANT Part 4 of 5 UPDATED FINAL SAFETY ANALYSIS REPORT Page: 1 of 29 Equipment Required to Shutdown Reactor (Unit 2)

(For High Energy Pipe Ruptures Outside the Containment)

Equip Id Equipment Description System Building Elev Room Rm#

Nuclear Instrumentation 2-NRI-1 Reactor Coolant Auxiliary 633 Control Room 123 Source Range Monitor Nuclear Instrumentation Nuclear 2-NRI-21 Containment 626 Reactor Cavity 105 Source Range Radiation Detector Instrumentation Reactor Cable Nuclear Instrumentation Nuclear 2-NRI-21-AMP Auxiliary 596 Tunnel, 25 Wide Range Radiation Amplifier Cabinet Instrumentation Quadrant #1 Nuclear Instrumentation Nuclear 2-NRI-21-PRCSR Auxiliary 633 Control Room 123 Wide Range Signal Processor Cabinet Instrumentation Nuclear Instrumentation Nuclear 2-NRI-23 Containment 626 Reactor Cavity 105 Source Range Radiation Detector Instrumentation Nuclear Instrumentation Reactor Cable Nuclear 2-NRI-23-AMP Source Range Radiation Detector NRI-23 Auxiliary 596 Tunnel, 25 Instrumentation Amplifier Cabinet Quadrant #1 Reactor Cable Nuclear Instrumentation Nuclear 2-NRI-23-ISOL Auxiliary 596 Tunnel, 25 Source Range Signal Isolator Cabinet Instrumentation Quadrant #1 Unit 2

UFSAR Revision 31.0 INDIANA MICHIGAN POWER Revised: 26.0 Table: 14.4.2-1 D. C. COOK NUCLEAR PLANT Part 4 of 5 UPDATED FINAL SAFETY ANALYSIS REPORT Page: 2 of 29 Equipment Required to Shutdown Reactor (Unit 2)

(For High Energy Pipe Ruptures Outside the Containment)

Equip Id Equipment Description System Building Elev Room Rm#

Nuclear Instrumentation Nuclear 2-NRI-23-PRCSR Auxiliary 633 Control Room 123 Source Range Signal Processor Cabinet Instrumentation Nuclear Instrumentation 2-NRI-5 Reactor Coolant Auxiliary 633 Control Room 123 Source Range Monitor Pressurizer 2-NRV-151 Pressurizer Train 'B' Pressure Relief Valve Reactor Coolant Containment 650 Enclosure, 81 Interior Pressurizer 2-NRV-152 Pressurizer Train 'B' Pressure Relief Valve Reactor Coolant Containment 650 Enclosure, 81 Interior Pressurizer Pressurizer OME-4 2-NRV-153 Reactor Coolant Containment 650 Enclosure, 81 Train 'A' Pressure Relief Valve Interior Pressurizer OME-4 Pressurizer 2-NSO-62 Post Accident Vent Train 'A' Solenoid Reactor Coolant Containment 650 Enclosure, 81 Valve Interior Unit 2

UFSAR Revision 31.0 INDIANA MICHIGAN POWER Revised: 26.0 Table: 14.4.2-1 D. C. COOK NUCLEAR PLANT Part 4 of 5 UPDATED FINAL SAFETY ANALYSIS REPORT Page: 3 of 29 Equipment Required to Shutdown Reactor (Unit 2)

(For High Energy Pipe Ruptures Outside the Containment)

Equip Id Equipment Description System Building Elev Room Rm#

Pressurizer 2-NSO-61 Post-Accident Vent Valve Reactor Coolant Containment 650 Enclosure, 81 Interior Pressurizer 2-NSO-63 Post-Accident Vent Valve Reactor Coolant Containment 650 Enclosure, 81 Interior Pressurizer OME-4 Pressurizer 2-NSO-64 Post Accident Vent Train 'B' Solenoid Reactor Coolant Containment 650 Enclosure, 81 Valve Interior Reactor Coolant Loop #1 Lower 2-NTP-110A Hot Leg Channel I Reactor Protection Reactor Coolant Containment 598 Containment, 60 Input Narrow Range Thermal Sensor Quadrant #1 Reactor Coolant Loop #1 Lower 2-NTP-110B Hot Leg Channel I Reactor Protection Reactor Coolant Containment 598 Containment, 60 Input Spare Narrow Range Thermal Sensor Quadrant #1 Reactor Coolant Loop #1 Lower 2-NTP-111A Hot Leg Channel I Reactor Protection Reactor Coolant Containment 598 Containment, 60 Input Narrow Range Thermal Sensor Quadrant #1 Unit 2

UFSAR Revision 31.0 INDIANA MICHIGAN POWER Revised: 26.0 Table: 14.4.2-1 D. C. COOK NUCLEAR PLANT Part 4 of 5 UPDATED FINAL SAFETY ANALYSIS REPORT Page: 4 of 29 Equipment Required to Shutdown Reactor (Unit 2)

(For High Energy Pipe Ruptures Outside the Containment)

Equip Id Equipment Description System Building Elev Room Rm#

Reactor Coolant Loop #1 Lower 2-NTP-111B Hot Leg Channel I Reactor Protection Reactor Coolant Containment 598 Containment, 60 Input Spare Narrow Range Thermal Sensor Quadrant #1 Reactor Coolant Loop #1 Lower 2-NTP-112A Hot Leg Channel I Reactor Protection Reactor Coolant Containment 598 Containment, 60 Input Narrow Range Thermal Sensor Quadrant #1 Reactor Coolant Loop #1 Lower 2-NTP-112B Hot Leg Channel I Reactor Protection Reactor Coolant Containment 598 Containment, 60 Input Spare Narrow Range Thermal Sensor Quadrant #1 Reactor Coolant Loop #2 Lower 2-NTP-120A Hot Leg Channel II Reactor Protection Reactor Coolant Containment 598 Containment, 61 Input Narrow Range Thermal Sensor Quadrant #2 Reactor Coolant Loop #2 Lower 2-NTP-120B Hot Leg Channel II Reactor Protection Reactor Coolant Containment 598 Containment, 61 Input Spare Narrow Range Thermal Sensor Quadrant #2 Reactor Coolant Loop #2 Lower 2-NTP-121A Hot Leg Channel II Reactor Protection Reactor Coolant Containment 598 Containment, 61 Input Narrow Range Thermal Sensor Quadrant #2 Unit 2

UFSAR Revision 31.0 INDIANA MICHIGAN POWER Revised: 26.0 Table: 14.4.2-1 D. C. COOK NUCLEAR PLANT Part 4 of 5 UPDATED FINAL SAFETY ANALYSIS REPORT Page: 5 of 29 Equipment Required to Shutdown Reactor (Unit 2)

(For High Energy Pipe Ruptures Outside the Containment)

Equip Id Equipment Description System Building Elev Room Rm#

Reactor Coolant Loop #2 Lower 2-NTP-121B Hot Leg Channel II Reactor Protection Reactor Coolant Containment 598 Containment, 61 Input Spare Narrow Range Thermal Sensor Quadrant #2 Reactor Coolant Loop #2 Lower 2-NTP-122A Hot Leg Channel II Reactor Protection Reactor Coolant Containment 598 Containment, 61 Input Narrow Range Thermal Sensor Quadrant #2 Reactor Coolant Loop #2 Lower 2-NTP-122B Hot Leg Channel II Reactor Protection Reactor Coolant Containment 598 Containment, 61 Input Spare Narrow Range Thermal Sensor Quadrant #2 Reactor Coolant Loop #3 Lower 2-NTP-130A Hot Leg Channel III Reactor Protection Reactor Coolant Containment 598 Containment, 62 Input Narrow Range Thermal Sensor Quadrant #3 Reactor Coolant Loop #3 Lower 2-NTP-130B Hot Leg Channel III Reactor Protection Reactor Coolant Containment 598 Containment, 62 Input Spare Narrow Range Thermal Sensor Quadrant #3 Reactor Coolant Loop #3 Lower 2-NTP-131A Hot Leg Channel III Reactor Protection Reactor Coolant Containment 598 Containment, 62 Input Narrow Range Thermal Sensor Quadrant #3 Unit 2

UFSAR Revision 31.0 INDIANA MICHIGAN POWER Revised: 26.0 Table: 14.4.2-1 D. C. COOK NUCLEAR PLANT Part 4 of 5 UPDATED FINAL SAFETY ANALYSIS REPORT Page: 6 of 29 Equipment Required to Shutdown Reactor (Unit 2)

(For High Energy Pipe Ruptures Outside the Containment)

Equip Id Equipment Description System Building Elev Room Rm#

Reactor Coolant Loop #3 Lower 2-NTP-131B Hot Leg Channel III Reactor Protection Reactor Coolant Containment 598 Containment, 62 Input Spare Narrow Range Thermal Sensor Quadrant #3 Reactor Coolant Loop #3 Lower 2-NTP-132A Hot Leg Channel III Reactor Protection Reactor Coolant Containment 598 Containment, 62 Input Narrow Range Thermal Sensor Quadrant #3 Reactor Coolant Loop #3 Lower 2-NTP-132B Hot Leg Channel III Reactor Protection Reactor Coolant Containment 598 Containment, 62 Input Spare Narrow Range Thermal Sensor Quadrant #3 Reactor Coolant Loop #4 Lower 2-NTP-140A Hot Leg Channel IV Reactor Protection Reactor Coolant Containment 598 Containment, 63 Input Narrow Range Thermal Sensor Quadrant #4 Reactor Coolant Loop #4 Lower 2-NTP-140B Hot Leg Channel IV Reactor Protection Reactor Coolant Containment 598 Containment, 63 Input Spare Narrow Range Thermal Sensor Quadrant #4 Reactor Coolant Loop #4 Lower 2-NTP-141A Hot Leg Channel IV Reactor Protection Reactor Coolant Containment 598 Containment, 63 Input Narrow Range Thermal Sensor Quadrant #4 Unit 2

UFSAR Revision 31.0 INDIANA MICHIGAN POWER Revised: 26.0 Table: 14.4.2-1 D. C. COOK NUCLEAR PLANT Part 4 of 5 UPDATED FINAL SAFETY ANALYSIS REPORT Page: 7 of 29 Equipment Required to Shutdown Reactor (Unit 2)

(For High Energy Pipe Ruptures Outside the Containment)

Equip Id Equipment Description System Building Elev Room Rm#

Reactor Coolant Loop #4 Lower 2-NTP-141B Hot Leg Channel IV Reactor Protection Reactor Coolant Containment 598 Containment, 63 Input Spare Narrow Range Thermal Sensor Quadrant #4 Reactor Coolant Loop #4 Lower 2-NTP-142A Hot Leg Channel IV Reactor Protection Reactor Coolant Containment 598 Containment, 63 Input Narrow Range Thermal Sensor Quadrant #4 Reactor Coolant Loop #4 Lower 2-NTP-142B Hot Leg Channel IV Reactor Protection Reactor Coolant Containment 598 Containment, 63 Input Spare Narrow Range Thermal Sensor Quadrant #4 Reactor Coolant Loop #1 Lower 2-NTP-210A Cold Leg Channel I Reactor Protection Reactor Coolant Containment 625 Containment, 60 Input Narrow Range Thermal Sensor Quadrant #1 Reactor Coolant Loop #1 Lower 2-NTP-210B Cold Leg Channel I Reactor Protection Reactor Coolant Containment 625 Containment, 60 Input Spare Narrow Range Thermal Sensor Quadrant #1 Reactor Coolant Loop #2 Lower 2-NTP-220A Cold Leg Channel II Reactor Protection Reactor Coolant Containment 617 Containment, 61 Input Narrow Range Thermal Sensor Quadrant #2 Unit 2

UFSAR Revision 31.0 INDIANA MICHIGAN POWER Revised: 26.0 Table: 14.4.2-1 D. C. COOK NUCLEAR PLANT Part 4 of 5 UPDATED FINAL SAFETY ANALYSIS REPORT Page: 8 of 29 Equipment Required to Shutdown Reactor (Unit 2)

(For High Energy Pipe Ruptures Outside the Containment)

Equip Id Equipment Description System Building Elev Room Rm#

Reactor Coolant Loop #2 Lower 2-NTP-220B Cold Leg Channel II Reactor Protection Reactor Coolant Containment 617 Containment, 61 Input Spare Narrow Range Thermal Sensor Quadrant #2 Reactor Coolant Loop #3 Lower 2-NTP-230A Cold Leg Channel III Reactor Protection Reactor Coolant Containment 617 Containment, 62 Input Narrow Range Thermal Sensor Quadrant #3 Reactor Coolant Loop #3 Lower 2-NTP-230B Cold Leg Channel III Reactor Protection Reactor Coolant Containment 617 Containment, 62 Input Spare Narrow Range Thermal Sensor Quadrant #3 Reactor Coolant Loop #4 Lower 2-NTP-240A Cold Leg Channel IV Reactor Protection Reactor Coolant Containment 625 Containment, 63 Input Narrow Range Thermal Sensor Quadrant #4 Reactor Coolant Loop #4 Lower 2-NTP-240B Cold Leg Channel IV Reactor Protection Reactor Coolant Containment 625 Containment, 63 Input Spare Narrow Range Thermal Sensor Quadrant #4 Diesel Generator, 2-OME-150-AB AB Emergency Diesel Generator Auxiliary 587 AB EDG Room 121 Control &

Instrumentation Unit 2

UFSAR Revision 31.0 INDIANA MICHIGAN POWER Revised: 26.0 Table: 14.4.2-1 D. C. COOK NUCLEAR PLANT Part 4 of 5 UPDATED FINAL SAFETY ANALYSIS REPORT Page: 9 of 29 Equipment Required to Shutdown Reactor (Unit 2)

(For High Energy Pipe Ruptures Outside the Containment)

Equip Id Equipment Description System Building Elev Room Rm#

Diesel Generator, 2-OME-150-CD CD Emergency Diesel Generator Auxiliary 587 CD EDG Room 122 Control &

Instrumentation Lower 2-OME-3-1 Steam Generator No. 1 Main Steam Containment 609 Containment, 60 Quadrant #1 Lower 2-OME-3-2 Steam Generator No. 2 Main Steam Containment 609 Containment, 61 Quadrant #2 Lower 2-OME-3-3 Steam Generator No. 3 Main Steam Containment 609 Containment, 62 Quadrant #3 Lower 2-OME-3-4 Steam Generator No. 4 Main Steam Containment 609 Containment, 63 Quadrant #4 East Essential Service Water Pump Essential Service East ESW Pump 2-OME-34E Screenhouse 591 135 PP-7E Discharge Strainer Water Room Unit 2

UFSAR Revision 31.0 INDIANA MICHIGAN POWER Revised: 26.0 Table: 14.4.2-1 D. C. COOK NUCLEAR PLANT Part 4 of 5 UPDATED FINAL SAFETY ANALYSIS REPORT Page: 10 of 29 Equipment Required to Shutdown Reactor (Unit 2)

(For High Energy Pipe Ruptures Outside the Containment)

Equip Id Equipment Description System Building Elev Room Rm#

West Essential Service Water Pump Essential Service West ESW 2-OME-34W Screenhouse 591 136 PP-7W Discharge Strainer Water Pump Room Auxiliary 2-OME-39 Auxiliary Feed Pump Turbine Feedwater/Main Turbine 591 TDAFP Room 49 Steam Starting Air Syst/Pilot Operated 4-Way 2-POV-1-AB Valve for Air Start of XRVs for Diesel Compressed Air Auxiliary 587 AB EDG Room 121 Engine Starting Air Syst/Pilot Operated 4-Way 2-POV-1-CD Valve for Air Start of XRVs for Diesel Compressed Air Auxiliary 587 CD EDG Room 122 Engine Starting Air Syst/Pilot Operated 4-Way 2-POV-2-AB Valve for Air Start of XRVs for Diesel Compressed Air Auxiliary 587 AB EDG Room 121 Engine Starting Air Syst/Pilot Operated 4-Way 2-POV-2-CD Valve for Air Start of XRVs for Diesel Compressed Air Auxiliary 587 CD EDG Room 122 Engine Unit 2

UFSAR Revision 31.0 INDIANA MICHIGAN POWER Revised: 26.0 Table: 14.4.2-1 D. C. COOK NUCLEAR PLANT Part 4 of 5 UPDATED FINAL SAFETY ANALYSIS REPORT Page: 11 of 29 Equipment Required to Shutdown Reactor (Unit 2)

(For High Energy Pipe Ruptures Outside the Containment)

Equip Id Equipment Description System Building Elev Room Rm#

Component 2-PP-10E East CCW Pump Auxiliary 609 609 Hallway 609 Cooling Water Component 2-PP-10W West CCW Pump Auxiliary 609 609 Hallway 609 Cooling Water 2-PP-120-AB Engine Driven Pump Diesel Fuel Oil Auxiliary 587 AB EDG Room 121 2-PP-120-CD Engine Driven Pump Diesel Fuel Oil Auxiliary 587 CD EDG Room 122 North Safety 2-PP-26N North Safety Injection Pump Safety Injection Auxiliary 587 Injection Pump 42 Room South Safety 2-PP-26S South Safety Injection Pump Safety Injection Auxiliary 587 Injection Pump 43 Room Residual Heat East RHR Pump 2-PP-35E East Residual Heat Removal Pump Auxiliary 573 54 Removal Room Residual Heat West RHR 2-PP-35W West Residual Heat Removal Pump Auxiliary 573 55 Removal Pump Room Unit 2

UFSAR Revision 31.0 INDIANA MICHIGAN POWER Revised: 26.0 Table: 14.4.2-1 D. C. COOK NUCLEAR PLANT Part 4 of 5 UPDATED FINAL SAFETY ANALYSIS REPORT Page: 12 of 29 Equipment Required to Shutdown Reactor (Unit 2)

(For High Energy Pipe Ruptures Outside the Containment)

Equip Id Equipment Description System Building Elev Room Rm#

East Motor Driven Auxiliary East MDAFP 2-PP-3E Turbine 591 50 Auxiliary Feedwater Pump Feedwater Room West Motor Driven Auxiliary West MDAFP 2-PP-3W Turbine 591 51 Auxiliary Feedwater Pump Feedwater Room Turbine Driven Auxiliary 2-PP-4 Turbine 591 TDAFP Room 49 Auxiliary Feed Pump Feedwater East Centrifugal (CVCS) 2-PP-50E East Centrifugal Charging Pump Auxiliary 587 Charging Pump 40 Charging Room West Centrifugal (CVCS) 2-PP-50W West Centrifugal Charging Pump Auxiliary 587 Charging Pump 41 Charging Room Essential Service East ESW Pump 2-PP-7E East Essential Service Water Pump Screenhouse 591 135 Water Room Essential Service West ESW 2-PP-7W West Essential Service Water Pump Screenhouse 591 136 Water Pump Room Control Room Air Conditioning Control Room Control Rm A/C 2-PP-82N Auxiliary 650 129 North Chill Water Circulation Pump Ventilation Room Unit 2

UFSAR Revision 31.0 INDIANA MICHIGAN POWER Revised: 26.0 Table: 14.4.2-1 D. C. COOK NUCLEAR PLANT Part 4 of 5 UPDATED FINAL SAFETY ANALYSIS REPORT Page: 13 of 29 Equipment Required to Shutdown Reactor (Unit 2)

(For High Energy Pipe Ruptures Outside the Containment)

Equip Id Equipment Description System Building Elev Room Rm#

Control Room Air Conditioning Control Room Control Rm A/C 2-PP-82S Auxiliary 650 129 South Chill Water Circulation Pump Ventilation Room Lower Containment Channel III Containment 612 Airlock 2-PPP-301 Auxiliary 612 12 Pressure Protection Transmitter Ventilation Area Lower Containment Channel II Containment 612 Airlock 2-PPP-302 Auxiliary 612 12 Pressure Protection Transmitter Ventilation Area Lower Containment Channel I Containment 612 Airlock 2-PPP-303 Auxiliary 612 12 Pressure Protection Transmitter Ventilation Area Pressure Regulator for Starting Air 2-PRV-1-AB Compressed Air Auxiliary 587 AB EDG Room 121 Solenoid 20-SV-1-AB Pressure Regulator for Starting Air 2-PRV-1-CD Compressed Air Auxiliary 587 AB EDG Room 121 Solenoid 20-SV-1-CD 2-PRZ Pressurizer Control Panel Reactor Coolant Auxiliary 633 Control Room 123 Traveling Screen 2-PS-A 600Vac Motor Control Center PS-A 600Vac Screenhouse 594 MCC Upper 221 Room Unit 2

UFSAR Revision 31.0 INDIANA MICHIGAN POWER Revised: 26.0 Table: 14.4.2-1 D. C. COOK NUCLEAR PLANT Part 4 of 5 UPDATED FINAL SAFETY ANALYSIS REPORT Page: 14 of 29 Equipment Required to Shutdown Reactor (Unit 2)

(For High Energy Pipe Ruptures Outside the Containment)

Equip Id Equipment Description System Building Elev Room Rm#

Traveling Screen 2-PS-D 600Vac Motor Control Center PS-D 600Vac Screenhouse 594 MCC Upper 221 Room Reactor Coolant Pump Seal Water Return (CVCS) Annulus -

2-QCM-250 Train 'A' Containment Isolation 4" Motor Containment 598 59 Letdown Quadrant #2 Operated Valve Reactor Coolant Pump Seal Water Return (CVCS) 2-QCM-350 Train 'B' Containment Isolation 4" Motor Auxiliary 591 Vestibule 28 Letdown Operated Valve Reactor Coolant Letdown Train 'B' (CVCS) 2-QCR-300 Auxiliary 591 Vestibule 28 Containment Isolation Valve Letdown (CVCS) Annulus -

2-QCR-301 CVCS Letdown Isolation Containment 598 59 Letdown Quadrant #2 Reactor Coolant RCP Seal Water Injection to Reactor Pump Seal 2-QFA-210 Coolant Pump PP-45-1 Low Flow Alarm Auxiliary 587 587 Hallway 587 Water Transmitter INJ/Leakoff Unit 2

UFSAR Revision 31.0 INDIANA MICHIGAN POWER Revised: 26.0 Table: 14.4.2-1 D. C. COOK NUCLEAR PLANT Part 4 of 5 UPDATED FINAL SAFETY ANALYSIS REPORT Page: 15 of 29 Equipment Required to Shutdown Reactor (Unit 2)

(For High Energy Pipe Ruptures Outside the Containment)

Equip Id Equipment Description System Building Elev Room Rm#

Reactor Coolant RCP Seal Water Injection to Reactor Pump Seal 2-QFA-220 Coolant Pump PP-45-2 Low Flow Alarm Auxiliary 587 587 Hallway 587 Water Transmitter INJ/Leakoff Reactor Coolant RCP Seal Water Injection to Reactor Pump Seal 2-QFA-230 Coolant Pump PP-45-3 Low Flow Alarm Auxiliary 587 587 Hallway 587 Water Transmitter INJ/Leakoff Reactor Coolant RCP Seal Water Injection to Reactor Pump Seal 2-QFA-240 Coolant Pump PP-45-4 Low Flow Alarm Auxiliary 587 587 Hallway 587 Water Transmitter INJ/Leakoff CVCS Charging Pumps Discharge Flow (CVCS) 2-QFI-200 Auxiliary 587 587 Hallway 587 Indicator Transmitter Charging Reciprocating CVCS Charging to Regenerative Heat (CVCS) 2-QMO-200 Auxiliary 587 Charging Pump 39 Exchanger Train 'A' Shutoff Valve Charging Room Unit 2

UFSAR Revision 31.0 INDIANA MICHIGAN POWER Revised: 26.0 Table: 14.4.2-1 D. C. COOK NUCLEAR PLANT Part 4 of 5 UPDATED FINAL SAFETY ANALYSIS REPORT Page: 16 of 29 Equipment Required to Shutdown Reactor (Unit 2)

(For High Energy Pipe Ruptures Outside the Containment)

Equip Id Equipment Description System Building Elev Room Rm#

Reciprocating CVCS Charging to Regenerative Heat (CVCS) 2-QMO-201 Auxiliary 587 Charging Pump 39 Exchanger Train 'B' Shutoff Valve Charging Room East Centrifugal Charging Pump Mini- East Centrifugal (CVCS) 2-QMO-225 Flow to RCP Seal Water Heat Exchanger Auxiliary 587 Charging Pump 40 Charging HE-11 2" Motor Operated Shutoff Valve Room West Centrifugal Charging Pump Mini- West Centrifugal (CVCS) 2-QMO-226 Flow to RCP Seal Water Heat Exchanger Auxiliary 587 Charging Pump 41 Charging HE-11 2" Motor Operated Shutoff Valve Room Reactor Coolant Letdown Volume Control Volume Control (CVCS) 2-QMO-451 Tank TK-10 to CVCS Charging Pumps Auxiliary 609 Tank East 19 Letdown Train 'A' Shutoff 4" Motor Operated Valve Hallway Reactor Coolant Letdown Volume Control Volume Control (CVCS) 2-QMO-452 Tank TK-10 to CVCS Charging Pumps Auxiliary 609 Tank East 19 Letdown Train 'B' Shutoff 4" Motor Operated Valve Hallway Reactor Coolant Reactor Coolant Pump #1 Seal #1 Leakoff Lower Pump Seal 2-QRV-10 to RCP Seal Water Return Filter QC-109 Containment 617 Containment, 60 Water 2" Air Operated Shutoff Valve Quadrant #1 INJ/Leakoff Unit 2

UFSAR Revision 31.0 INDIANA MICHIGAN POWER Revised: 26.0 Table: 14.4.2-1 D. C. COOK NUCLEAR PLANT Part 4 of 5 UPDATED FINAL SAFETY ANALYSIS REPORT Page: 17 of 29 Equipment Required to Shutdown Reactor (Unit 2)

(For High Energy Pipe Ruptures Outside the Containment)

Equip Id Equipment Description System Building Elev Room Rm#

Reactor Coolant Reactor Coolant Pumps Startup Seal Pump Seal Annulus -

2-QRV-150 System Bypass to Seal Water Return Filter Containment 598 59 Water Quadrant #2 QC-109 0.75" Air Operated Shutoff Valve INJ/Leakoff Reactor Coolant Reactor Coolant Pump #2 Seal #1 Leakoff Lower Pump Seal 2-QRV-20 to RCP Seal Water Return Filter QC-109 Containment 625 Containment, 61 Water 2" Air Operated Shutoff Globe Valve Quadrant #2 INJ/Leakoff CVCS Centrifugal Charging Pumps Reciprocating (CVCS) 2-QRV-251 Discharge Flow 3" Air Operated Control Auxiliary 587 Charging Pump 39 Charging Globe Valve Room Reactor Coolant Reactor Coolant Pump #3 Seal #1 Leakoff Lower Pump Seal 2-QRV-30 to RCP Seal Water Return Filter QC-109 Containment 612 Containment, 62 Water 2" Air Operated Shutoff Globe Valve Quadrant #3 INJ/Leakoff Reactor Coolant Reactor Coolant Pump #4 Seal #1 Leakoff Lower Pump Seal 2-QRV-40 to RCP Seal Water Return Filter QC-109 Containment 612 Containment, 63 Water 2" Air Operated Shutoff Globe Valve Quadrant #4 INJ/Leakoff Unit 2

UFSAR Revision 31.0 INDIANA MICHIGAN POWER Revised: 26.0 Table: 14.4.2-1 D. C. COOK NUCLEAR PLANT Part 4 of 5 UPDATED FINAL SAFETY ANALYSIS REPORT Page: 18 of 29 Equipment Required to Shutdown Reactor (Unit 2)

(For High Energy Pipe Ruptures Outside the Containment)

Equip Id Equipment Description System Building Elev Room Rm#

AB Emergency Diesel Diesel Inner Plant 2-QT-100-AB Grounds 609 244 Air Intake Filter Combustion Air Grounds CD Emergency Diesel Diesel Inner Plant 2-QT-100-CD Grounds 609 244 Air Intake Filter Combustion Air Grounds AB Emergency Diesel Diesel 2-QT-101-AB Auxiliary 587 AB EDG Room 121 Air Intake Silencer Combustion Air CD Emergency Diesel Diesel 2-QT-101-CD Auxiliary 587 CD EDG Room 122 Air Intake Silencer Combustion Air AB Emergency Diesel Diesel Inner Plant 2-QT-104-AB Grounds 609 244 Exhaust Silencer Combustion Air Grounds CD Emergency Diesel Diesel Inner Plant 2-QT-104-CD Grounds 609 244 Exhaust Silencer Combustion Air Grounds AB EDG Fuel AB Emergency Diesel 2-QT-106-AB1 Diesel Fuel Oil Auxiliary 587 Oil Transfer 126 Fuel Oil Transfer Pump #1 Pump Room AB EDG Fuel AB Emergency Diesel 2-QT-106-AB2 Diesel Fuel Oil Auxiliary 587 Oil Transfer 126 Fuel Oil Transfer Pump #2 Pump Room Unit 2

UFSAR Revision 31.0 INDIANA MICHIGAN POWER Revised: 26.0 Table: 14.4.2-1 D. C. COOK NUCLEAR PLANT Part 4 of 5 UPDATED FINAL SAFETY ANALYSIS REPORT Page: 19 of 29 Equipment Required to Shutdown Reactor (Unit 2)

(For High Energy Pipe Ruptures Outside the Containment)

Equip Id Equipment Description System Building Elev Room Rm#

CD EDG Fuel CD Emergency Diesel 2-QT-106-CD1 Diesel Fuel Oil Auxiliary 587 Oil Transfer 125 Fuel Oil Transfer Pump #1 Pump Room CD EDG Fuel CD Emergency Diesel 2-QT-106-CD2 Diesel Fuel Oil Auxiliary 587 Oil Transfer 125 Fuel Oil Transfer Pump #2 Pump Room AB Emergency Diesel 2-QT-107-AB Diesel Fuel Oil Auxiliary 587 AB EDG Room 121 Fuel Oil Day Tank CD Emergency Diesel 2-QT-107-CD Diesel Fuel Oil Auxiliary 587 CD EDG Room 122 Fuel Oil Day Tank AB Emergency Diesel 2-QT-110-AB Diesel Lube Oil Auxiliary 587 AB EDG Room 121 Lube Oil Cooler CD Emergency Diesel 2-QT-110-CD Diesel Lube Oil Auxiliary 587 CD EDG Room 122 Lube Oil Cooler AB Emergency Diesel AB EDG Lube 2-QT-111-AB Diesel Lube Oil Auxiliary 579 257 Lube Oil Before and After Pump Oil Pit CD Emergency Diesel CD EDG Lube 2-QT-111-CD Diesel Lube Oil Auxiliary 579 258 Lube Oil Before and After Pump Oil Pit Unit 2

UFSAR Revision 31.0 INDIANA MICHIGAN POWER Revised: 26.0 Table: 14.4.2-1 D. C. COOK NUCLEAR PLANT Part 4 of 5 UPDATED FINAL SAFETY ANALYSIS REPORT Page: 20 of 29 Equipment Required to Shutdown Reactor (Unit 2)

(For High Energy Pipe Ruptures Outside the Containment)

Equip Id Equipment Description System Building Elev Room Rm#

AB Emergency Diesel AB EDG Lube 2-QT-112-AB Diesel Lube Oil Auxiliary 579 257 Full Flow Lube Oil Filter Oil Pit CD Emergency Diesel CD EDG Lube 2-QT-112-CD Diesel Lube Oil Auxiliary 579 258 Full Flow Lube Oil Filter Oil Pit AB Emergency Diesel AB EDG Lube 2-QT-113-AB1 Diesel Lube Oil Auxiliary 579 257 Full Flow Lube Oil Strainer #1 Oil Pit AB Emergency Diesel AB EDG Lube 2-QT-113-AB2 Diesel Lube Oil Auxiliary 579 257 Full Flow Lube Oil Strainer #2 Oil Pit CD Emergency Diesel CD EDG Lube 2-QT-113-CD1 Diesel Lube Oil Auxiliary 579 258 Full Flow Lube Oil Strainer #1 Oil Pit CD Emergency Diesel CD EDG Lube 2-QT-113-CD2 Diesel Lube Oil Auxiliary 579 258 Full Flow Lube Oil Strainer #2 Oil Pit AB Emergency Diesel 2-QT-114-AB Lube Oil Cooler QT-110-AB Lube Oil Diesel Lube Oil Auxiliary 587 AB EDG Room 121 Thermostatic Inlet/Bypass Valve CD Emergency Diesel 2-QT-114-CD Lube Oil Cooler QT-110-CD Lube Oil Diesel Lube Oil Auxiliary 587 CD EDG Room 122 Thermostatic Inlet/Bypass Valve Unit 2

UFSAR Revision 31.0 INDIANA MICHIGAN POWER Revised: 26.0 Table: 14.4.2-1 D. C. COOK NUCLEAR PLANT Part 4 of 5 UPDATED FINAL SAFETY ANALYSIS REPORT Page: 21 of 29 Equipment Required to Shutdown Reactor (Unit 2)

(For High Energy Pipe Ruptures Outside the Containment)

Equip Id Equipment Description System Building Elev Room Rm#

AB Emergency Diesel AB EDG Lube 2-QT-115-AB Diesel Lube Oil Auxiliary 579 257 Lube Oil Sump Tank Oil Pit CD Emergency Diesel CD EDG Lube 2-QT-115-CD Diesel Lube Oil Auxiliary 579 258 Lube Oil Sump Tank Oil Pit AB Emergency Diesel AB EDG Lube 2-QT-116-AB Diesel Lube Oil Auxiliary 579 257 Lube Oil Heater Tank Oil Pit CD Emergency Diesel CD EDG Lube 2-QT-116-CD Diesel Lube Oil Auxiliary 579 258 Lube Oil Heater Tank Oil Pit AB Emergency Diesel AB EDG 2-QT-117-AB Diesel Lube Oil Auxiliary 579 257 Lube Oil Heater QT-116-AB Pump Lube Oil Pit CD Emergency Diesel CD EDG 2-QT-117-CD Diesel Lube Oil Auxiliary 579 258 Lube Oil Heater QT-116-CD Pump Lube Oil Pit AB Emergency Diesel AB EDG 2-QT-118-AB Diesel Lube Oil Auxiliary 579 257 Bypass Lube Oil Filter Lube Oil Pit CD Emergency Diesel CD EDG 2-QT-118-CD Diesel Lube Oil Auxiliary 579 258 Bypass Lube Oil Filter Lube Oil Pit Unit 2

UFSAR Revision 31.0 INDIANA MICHIGAN POWER Revised: 26.0 Table: 14.4.2-1 D. C. COOK NUCLEAR PLANT Part 4 of 5 UPDATED FINAL SAFETY ANALYSIS REPORT Page: 22 of 29 Equipment Required to Shutdown Reactor (Unit 2)

(For High Energy Pipe Ruptures Outside the Containment)

Equip Id Equipment Description System Building Elev Room Rm#

AB Emergency Diesel AB EDG 2-QT-119-AB Diesel Lube Oil Auxiliary 579 257 Bypass Lube Oil Filter QT-118-AB Pump Lube Oil Pit CD Emergency Diesel CD EDG 2-QT-119-CD Diesel Lube Oil Auxiliary 579 258 Bypass Lube Oil Filter QT-118-CD Pump Lube Oil Pit AB Emergency Diesel Diesel Jacket 2-QT-130-AB1 Auxiliary 587 AB EDG Room 121 Jacket Water Pump #1 Water AB Emergency Diesel Diesel Jacket 2-QT-130-AB2 Auxiliary 587 AB EDG Room 121 Jacket Water Pump #2 Water CD Emergency Diesel Diesel Jacket 2-QT-130-CD1 Auxiliary 587 CD EDG Room 122 Jacket Water Pump #1 Water CD Emergency Diesel Diesel Jacket 2-QT-130-CD2 Auxiliary 587 CD EDG Room 122 Jacket Water Pump #2 Water AB Emergency Diesel Diesel Jacket 2-QT-131-AB Auxiliary 587 AB EDG Room 121 Jacket Water Cooler Water CD Emergency Diesel Diesel Jacket 2-QT-131-CD Auxiliary 587 CD EDG Room 122 Jacket Water Cooler Water Unit 2

UFSAR Revision 31.0 INDIANA MICHIGAN POWER Revised: 26.0 Table: 14.4.2-1 D. C. COOK NUCLEAR PLANT Part 4 of 5 UPDATED FINAL SAFETY ANALYSIS REPORT Page: 23 of 29 Equipment Required to Shutdown Reactor (Unit 2)

(For High Energy Pipe Ruptures Outside the Containment)

Equip Id Equipment Description System Building Elev Room Rm#

AB Emergency Diesel Diesel Jacket 2-QT-132-AB Jacket Water Cooler QT-131-AB Jacket Auxiliary 587 AB EDG Room 121 Water Water Thermostatic Inlet/Bypass Valve CD Emergency Diesel Diesel Jacket 2-QT-132-CD Jacket Water Cooler QT-131-CD Jacket Auxiliary 587 CD EDG Room 122 Water Water Thermostatic Inlet/Bypass AB Emergency Diesel Diesel Jacket 2-QT-133-AB Auxiliary 587 AB EDG Room 121 Jacket Water Surge Tank Water CD Emergency Diesel Diesel Jacket 2-QT-133-CD Auxiliary 587 CD EDG Room 122 Jacket Water Surge Tank Water AB Emergency Diesel Diesel Jacket 2-QT-134-AB Auxiliary 587 AB EDG Room 121 Auxiliary Jacket Water Heater Water CD Emergency Diesel Diesel Jacket 2-QT-134-CD Auxiliary 587 CD EDG Room 122 Auxiliary Jacket Water Heater (Tank) Water AB Emergency Diesel Diesel Jacket 2-QT-135-AB Auxiliary 587 AB EDG Room 121 Auxiliary Jacket Water Pump Water CD Emergency Diesel Diesel Jacket 2-QT-135-CD Auxiliary 587 CD EDG Room 122 Auxiliary Jacket Water Pump Water Unit 2

UFSAR Revision 31.0 INDIANA MICHIGAN POWER Revised: 26.0 Table: 14.4.2-1 D. C. COOK NUCLEAR PLANT Part 4 of 5 UPDATED FINAL SAFETY ANALYSIS REPORT Page: 24 of 29 Equipment Required to Shutdown Reactor (Unit 2)

(For High Energy Pipe Ruptures Outside the Containment)

Equip Id Equipment Description System Building Elev Room Rm#

AB Emergency Diesel Diesel Starting 2-QT-141-AB1 Auxiliary 587 AB EDG Room 121 Starting Air Receiver #1 Air AB Emergency Diesel Diesel Starting 2-QT-141-AB2 Auxiliary 587 AB EDG Room 121 Starting Air Receiver #2 Air CD Emergency Diesel Diesel Starting 2-QT-141-CD1 Auxiliary 587 CD EDG Room 122 Starting Air Receiver #1 Air CD Emergency Diesel Diesel Starting 2-QT-141-CD2 Auxiliary 587 CD EDG Room 122 Starting Air Receiver #2 Air AB Emergency Diesel Diesel Control 2-QT-143-AB1 Auxiliary 587 AB EDG Room 121 Control Air Dryer #1 Air AB Emergency Diesel Diesel Control 2-QT-143-AB2 Auxiliary 587 AB EDG Room 121 Control Air Dryer #2 Air CD Emergency Diesel Diesel Control 2-QT-143-CD1 Auxiliary 587 CD EDG Room 122 Control Air Dryer #1 Air CD Emergency Diesel Diesel Control 2-QT-143-CD2 Auxiliary 587 CD EDG Room 122 Control Air Dryer #2 Air Unit 2

UFSAR Revision 31.0 INDIANA MICHIGAN POWER Revised: 26.0 Table: 14.4.2-1 D. C. COOK NUCLEAR PLANT Part 4 of 5 UPDATED FINAL SAFETY ANALYSIS REPORT Page: 25 of 29 Equipment Required to Shutdown Reactor (Unit 2)

(For High Energy Pipe Ruptures Outside the Containment)

Equip Id Equipment Description System Building Elev Room Rm#

AB Emergency Diesel 2-QT-144-AB Diesel Fuel Oil Auxiliary 587 AB EDG Room 121 Fuel Oil Transfer Filter CD Emergency Diesel 2-QT-144-CD Diesel Fuel Oil Auxiliary 587 CD EDG Room 122 Fuel Oil Transfer Filter AB Emergency Diesel Diesel 2-QT-502-AB Auxiliary 587 AB EDG Room 121 Turbocharger Combustion Air CD Emergency Diesel Diesel 2-QT-502-CD Auxiliary 587 CD EDG Room 122 Turbocharger Combustion Air Auxiliary Turbine Driven Aux Feed Pump 2-QT-506 Feedwater/Main Turbine 591 TDAFP Room 49 PP-4 Trip and Throttle Valve Steam 2-QT-507 TDAFP Governor Valve Main Steam Turbine 591 TDAFP Room 49 Rod Control and 2-RC Reactor Control Rods Control Panel Auxiliary 633 Control Room 123 Instrumentation East RHR Heat Residual Heat 2-RH-117 RHR Bypass Isolation Manual Valve Auxiliary 609 Exchanger 5 Removal Room Unit 2

UFSAR Revision 31.0 INDIANA MICHIGAN POWER Revised: 26.0 Table: 14.4.2-1 D. C. COOK NUCLEAR PLANT Part 4 of 5 UPDATED FINAL SAFETY ANALYSIS REPORT Page: 26 of 29 Equipment Required to Shutdown Reactor (Unit 2)

(For High Energy Pipe Ruptures Outside the Containment)

Equip Id Equipment Description System Building Elev Room Rm#

Residual Heat 2-RHR Residual Heat Removal Control Panel Auxiliary 633 Control Room 123 Removal Reactor Protection Channel I Reactor 2-RPC-I Auxiliary 633 Control Room 123 Cabinet #1, 2, 3 & 4 Protection Reactor Protection Channel II Reactor 2-RPC-II Auxiliary 633 Control Room 123 Cabinet #5, 6 & 7 Protection Reactor Protection Channel III Reactor 2-RPC-III Auxiliary 633 Control Room 123 Cabinet #9, 10 & 11 Protection Reactor Protection Channel IV Reactor 2-RPC-IV Auxiliary 633 Control Room 123 Cabinet #12 Protection Reactor Protection and Safeguard Reactor 2-RPS-A Auxiliary 633 Control Room 123 Actuation Train 'A' Cabinet Protection Reactor Protection and Safeguard Reactor 2-RPS-B Auxiliary 633 Control Room 123 Actuation Train 'B' Cabinet Protection Reactor Protection and Safeguard Reactor 2-RPSX-A Auxiliary 633 Control Room 123 Actuation Train "A" Auxiliary Cabinet Protection Unit 2

UFSAR Revision 31.0 INDIANA MICHIGAN POWER Revised: 26.0 Table: 14.4.2-1 D. C. COOK NUCLEAR PLANT Part 4 of 5 UPDATED FINAL SAFETY ANALYSIS REPORT Page: 27 of 29 Equipment Required to Shutdown Reactor (Unit 2)

(For High Energy Pipe Ruptures Outside the Containment)

Equip Id Equipment Description System Building Elev Room Rm#

Reactor Protection and Safeguard Reactor 2-RPSX-B Auxiliary 633 Control Room 123 Actuation Train "B" Auxiliary Cabinet Protection 2-SA Station Auxiliaries Control Panel 4160Vac Auxiliary 633 Control Room 123 Steam Generator and Auxiliary Feed Pump Auxiliary 2-SG Auxiliary 633 Control Room 123 Control Panel Feedwater East Residual Heat Containment 2-SI-152N RHR to SI Pumps Check Valve Containment 612 72 Removal Lower Vent Room West Residual Heat Containment 2-SI-152S RHR to SI Pumps Check Valve Containment 612 73 Removal Lower Vent Room Boron Injection to Charging Pump 2-SI-210 Boron Injection Auxiliary 612 BIT Room 16 Crosstie Check Valve 250Vdc Train 'A' Nuclear 2-SSV-A1 250Vdc Auxiliary 587 36 Nuclear Sampling Feeder Panel #1 Sampling Room Unit 2

UFSAR Revision 31.0 INDIANA MICHIGAN POWER Revised: 26.0 Table: 14.4.2-1 D. C. COOK NUCLEAR PLANT Part 4 of 5 UPDATED FINAL SAFETY ANALYSIS REPORT Page: 28 of 29 Equipment Required to Shutdown Reactor (Unit 2)

(For High Energy Pipe Ruptures Outside the Containment)

Equip Id Equipment Description System Building Elev Room Rm#

250Vdc Train 'A' Nuclear 2-SSV-A2 250Vdc Auxiliary 587 36 Nuclear Sampling Feeder Panel #2 Sampling Room 250Vdc Train 'B' Nuclear 2-SSV-B 250Vdc Auxiliary 587 36 Nuclear Sampling Feeder Panel Sampling Room Residual Heat Removal to Reactor Coolant Residual Heat Annulus -

2-SV-102 Containment 598 59 Loops #2 & #3 Cold Legs Safety Valve Removal Quadrant #2 Reactor Coolant Loop #2 Residual Heat Annulus -

2-SV-103 Hot Leg to Residual Heat Removal Pumps Containment 598 59 Removal Quadrant #2 Safety Valve East RHR Heat East Residual Heat Removal Heat Residual Heat 2-SV-104E Auxiliary 609 Exchanger 5 Exchanger HE-17E Outlet Safety Valve Removal Room West RHR Heat West Residual Heat Removal Heat Residual Heat 2-SV-104W Auxiliary 609 Exchanger 6 Exchanger HE-17W Outlet Safety Valve Removal Room 2-XTC-301 & 2-XTC-302 Control Air 2-SV-120-AB Control Air Auxiliary 587 AB EDG Room 121 Safety Valve Unit 2

UFSAR Revision 31.0 INDIANA MICHIGAN POWER Revised: 26.0 Table: 14.4.2-1 D. C. COOK NUCLEAR PLANT Part 4 of 5 UPDATED FINAL SAFETY ANALYSIS REPORT Page: 29 of 29 Equipment Required to Shutdown Reactor (Unit 2)

(For High Energy Pipe Ruptures Outside the Containment)

Equip Id Equipment Description System Building Elev Room Rm#

2-XTC-306 and 2-XTC-307 Control Air 2-SV-120-CD Control Air Auxiliary 587 CD EDG Room 122 Safety Valve AB Emergency Diesel Diesel Starting 2-SV-139-AB Auxiliary 587 AB EDG Room 121 Starting Air to Turbocharger Safety Valve Air CD Emergency Diesel Diesel Starting 2-SV-139-CD Auxiliary 587 CD EDG Room 122 Starting Air to Turbocharger Safety Valve Air Turbine Driven Aux Feed Pump Auxiliary 2-SV-140-1 Governor Oil Cooler Cooling Water Inlet Turbine 591 TDAFP Room 49 Feedwater Safety Valve Turbine Driven Aux Feed Pump Oil Auxiliary 2-SV-140-2 Turbine 591 TDAFP Room 49 Cooler Cooling Water Inlet Safety Valve Feedwater East Motor Driven Auxiliary Feedwater Auxiliary East MDAFP 2-SV-169E Turbine 591 50 Pump PP-3E Suction Safety Valve Feedwater Room West Motor Driven Auxiliary Feed Pump Auxiliary West MDAFP 2-SV-169W Turbine 591 51 PP-3W Suction Safety Valve Feedwater Room Unit 2

UFSAR Revision 31.0 INDIANA MICHIGAN POWER Revised: 27.0 Table: 14.4.2-1 D. C. COOK NUCLEAR PLANT Part 5 of 5 UPDATED FINAL SAFETY ANALYSIS REPORT Page: 1 of 29 Equipment Required to Shutdown Reactor (Unit 2)

(For High Energy Pipe Ruptures Outside the Containment)

Equip Id Equipment Description System Building Elev Room Rm#

Steam Generator OME-3-1 East Main Steam 2-SV-1A-1 Main Steam Auxiliary 633 10 Safety Valve 1A Stop Enclosure West Main Steam Generator OME-3-2 2-SV-1A-2 Main Steam Auxiliary 633 Steam Stop 9 Safety Valve 1A Enclosure West Main Steam Generator OME-3-3 2-SV-1A-3 Main Steam Auxiliary 633 Steam Stop 9 Safety Valve 1A Enclosure Steam Generator OME-3-4 East Main Steam 2-SV-1A-4 Main Steam Auxiliary 633 10 Safety Valve 1A Stop Enclosure Steam Generator OME-3-1 East Main Steam 2-SV-1B-1 Main Steam Auxiliary 633 10 Safety Valve 1B Stop Enclosure West Main Steam Generator OME-3-2 2-SV-1B-2 Main Steam Auxiliary 633 Steam Stop 9 Safety Valve 1B Enclosure Unit 2

UFSAR Revision 31.0 INDIANA MICHIGAN POWER Revised: 27.0 Table: 14.4.2-1 D. C. COOK NUCLEAR PLANT Part 5 of 5 UPDATED FINAL SAFETY ANALYSIS REPORT Page: 2 of 29 Equipment Required to Shutdown Reactor (Unit 2)

(For High Energy Pipe Ruptures Outside the Containment)

Equip Id Equipment Description System Building Elev Room Rm#

West Main Steam Generator OME-3-3 2-SV-1B-3 Main Steam Auxiliary 633 Steam Stop 9 Safety Valve 1B Enclosure Steam Generator OME-3-4 East Main Steam 2-SV-1B-4 Main Steam Auxiliary 633 10 Safety Valve 1B Stop Enclosure AB Emergency Diesel 2-SV-200-AB Fuel Oil Manifolds to Fuel Oil Day Tank Diesel Fuel Oil Auxiliary 587 AB EDG Room 121 Safety Valve CD Emergency Diesel 2-SV-200-CD Fuel Oil Manifolds to Fuel Oil Day Tank Diesel Fuel Oil Auxiliary 587 CD EDG Room 122 Safety Valve AB Emergency Diesel 2-SV-201-AB1 Front Bank Fuel Oil Manifold Safety Diesel Fuel Oil Auxiliary 587 CD EDG Room 122 Valve AB Emergency Diesel 2-SV-201-AB2 Rear Bank Fuel Oil Manifold Safety Diesel Fuel Oil Auxiliary 587 AB EDG Room 121 Valve Unit 2

UFSAR Revision 31.0 INDIANA MICHIGAN POWER Revised: 27.0 Table: 14.4.2-1 D. C. COOK NUCLEAR PLANT Part 5 of 5 UPDATED FINAL SAFETY ANALYSIS REPORT Page: 3 of 29 Equipment Required to Shutdown Reactor (Unit 2)

(For High Energy Pipe Ruptures Outside the Containment)

Equip Id Equipment Description System Building Elev Room Rm#

CD Emergency Diesel 2-SV-201-CD1 Front Bank Fuel Oil Manifold Safety Diesel Fuel Oil Auxiliary 587 CD EDG Room 122 Valve CD Emergency Diesel 2-SV-201-CD2 Diesel Fuel Oil Auxiliary 587 CD EDG Room 122 Rear Bank Fuel Oil Manifold Safety Valve Steam Generator OME-3-1 East Main Steam 2-SV-2A-1 Main Steam Auxiliary 633 10 Safety Valve 2A Stop Enclosure West Main Steam Generator OME-3-2 2-SV-2A-2 Main Steam Auxiliary 633 Steam Stop 9 Safety Valve 2A Enclosure West Main Steam Generator OME-3-3 2-SV-2A-3 Main Steam Auxiliary 633 Steam Stop 9 Safety Valve 2A Enclosure Steam Generator OME-3-4 East Main Steam 2-SV-2A-4 Main Steam Auxiliary 633 10 Safety Valve 2A Stop Enclosure Steam Generator OME-3-1 East Main Steam 2-SV-2B-1 Main Steam Auxiliary 633 10 Safety Valve 2B Stop Enclosure Unit 2

UFSAR Revision 31.0 INDIANA MICHIGAN POWER Revised: 27.0 Table: 14.4.2-1 D. C. COOK NUCLEAR PLANT Part 5 of 5 UPDATED FINAL SAFETY ANALYSIS REPORT Page: 4 of 29 Equipment Required to Shutdown Reactor (Unit 2)

(For High Energy Pipe Ruptures Outside the Containment)

Equip Id Equipment Description System Building Elev Room Rm#

West Main Steam Generator OME-3-2 2-SV-2B-2 Main Steam Auxiliary 633 Steam Stop 9 Safety Valve 2B Enclosure West Main Steam Generator OME-3-3 2-SV-2B-3 Main Steam Auxiliary 633 Steam Stop 9 Safety Valve 2B Enclosure Steam Generator OME-3-4 East Main Steam 2-SV-2B-4 Main Steam Auxiliary 633 10 Safety Valve 2B Stop Enclosure Steam Generator OME-3-1 East Main Steam 2-SV-3-1 Main Steam Auxiliary 633 10 Safety Valve #3 Stop Enclosure West Main Steam Generator OME-3-2 2-SV-3-2 Main Steam Auxiliary 633 Steam Stop 9 Safety Valve #3 Enclosure West Main Steam Generator OME-3-3 2-SV-3-3 Main Steam Auxiliary 633 Steam Stop 9 Safety Valve #3 Enclosure Unit 2

UFSAR Revision 31.0 INDIANA MICHIGAN POWER Revised: 27.0 Table: 14.4.2-1 D. C. COOK NUCLEAR PLANT Part 5 of 5 UPDATED FINAL SAFETY ANALYSIS REPORT Page: 5 of 29 Equipment Required to Shutdown Reactor (Unit 2)

(For High Energy Pipe Ruptures Outside the Containment)

Equip Id Equipment Description System Building Elev Room Rm#

Steam Generator OME-3-4 East Main Steam 2-SV-3-4 Main Steam Auxiliary 633 10 Safety Valve #3 Stop Enclosure Pressurizer Pressurizer OME-4 2-SV-45A Reactor Coolant Containment 650 Enclosure, 81 Safety Valve 'A' Interior Pressurizer Pressurizer OME-4 2-SV-45B Reactor Coolant Containment 650 Enclosure, 81 Safety Valve 'B' Interior Pressurizer Pressurizer OME-4 2-SV-45C Reactor Coolant Containment 650 Enclosure, 81 Safety Valve 'C' Interior Reactor Coolant RC Pumps Seal #1 and Startup Seal Pump Seal Annulus -

2-SV-50 System Bypass to Seal Water Return Containment 598 56 Water Quadrant #3 Filters Safety Valve INJ/Leakoff Seal Water Heat Reactor Coolant Pump Seal Water Heat (CVCS) 2-SV-54 Auxiliary 609 Exchanger 18 Exchanger HE-11 Safety Valve Letdown Room Unit 2

UFSAR Revision 31.0 INDIANA MICHIGAN POWER Revised: 27.0 Table: 14.4.2-1 D. C. COOK NUCLEAR PLANT Part 5 of 5 UPDATED FINAL SAFETY ANALYSIS REPORT Page: 6 of 29 Equipment Required to Shutdown Reactor (Unit 2)

(For High Energy Pipe Ruptures Outside the Containment)

Equip Id Equipment Description System Building Elev Room Rm#

Reciprocating CVCS Charging Pumps Suction Header (CVCS) 2-SV-56 Auxiliary 587 Charging Pump 39 Safety Valve Charging Room AB Emergency Diesel Diesel Jacket 2-SV-61-AB Auxiliary Jacket Water Heater QT-134-AB Auxiliary 587 AB EDG Room 121 Water Safety Valve CD Emergency Diesel Diesel Jacket 2-SV-61-CD Auxiliary Jacket Water Heater QT-134-CD Auxiliary 587 CD EDG Room 122 Water Safety Valve AB Emergency Diesel Diesel Starting 2-SV-78-AB1 Starting Air Receiver QT-141-AB1 Safety Auxiliary 587 AB EDG Room 121 Air Valve AB Emergency Diesel Diesel Starting 2-SV-78-AB2 Starting Air Receiver QT-141-AB2 Safety Auxiliary 587 AB EDG Room 121 Air Valve CD Emergency Diesel Diesel Starting 2-SV-78-CD1 Starting Air Receiver QT-141-CD1 Safety Auxiliary 587 CD EDG Room 122 Air Valve Unit 2

UFSAR Revision 31.0 INDIANA MICHIGAN POWER Revised: 27.0 Table: 14.4.2-1 D. C. COOK NUCLEAR PLANT Part 5 of 5 UPDATED FINAL SAFETY ANALYSIS REPORT Page: 7 of 29 Equipment Required to Shutdown Reactor (Unit 2)

(For High Energy Pipe Ruptures Outside the Containment)

Equip Id Equipment Description System Building Elev Room Rm#

CD Emergency Diesel Diesel Starting 2-SV-78-CD2 Starting Air Receiver QT-141-CD2 Safety Auxiliary 587 CD EDG Room 122 Air Valve AB Emergency Diesel Diesel Starting 2-SV-79-AB1 Control Air Dryer QT-143-AB1 Safety Auxiliary 587 AB EDG Room 121 Air Valve AB Emergency Diesel Diesel Starting 2-SV-79-AB2 Control Air Dryer QT-143-AB2 Safety Auxiliary 587 AB EDG Room 121 Air Valve CD Emergency Diesel Diesel Starting 2-SV-79-CD1 Control Air Dryer QT-143-CD1 Safety Auxiliary 587 CD EDG Room 122 Air Valve CD Emergency Diesel Diesel Starting 2-SV-79-CD2 Control Air Dryer QT-143-CD2 Safety Auxiliary 587 CD EDG Room 122 Air Valve South Safety Safety Injection Pumps 2-SV-96 Safety Injection Auxiliary 587 Injection Pump 43 Suction Header Safety Valve Room Unit 2

UFSAR Revision 31.0 INDIANA MICHIGAN POWER Revised: 27.0 Table: 14.4.2-1 D. C. COOK NUCLEAR PLANT Part 5 of 5 UPDATED FINAL SAFETY ANALYSIS REPORT Page: 8 of 29 Equipment Required to Shutdown Reactor (Unit 2)

(For High Energy Pipe Ruptures Outside the Containment)

Equip Id Equipment Description System Building Elev Room Rm#

Boron Injection Tank TK-11 2-SV-97 Boron Injection Auxiliary 612 BIT Room 16 Outlet Safety Valve North Safety North Safety Injection Pump PP-26N 2-SV-98N Safety Injection Auxiliary 587 Injection Pump 42 Discharge Header Safety Valve Room South Safety South Safety Injection Pump PP-26S 2-SV-98S Safety Injection Auxiliary 587 Injection Pump 43 Discharge Header Safety Valve Room 4kv Room - AB 2-T21A 4kv Bus T21A Switchgear 4160Vac Auxiliary 609 4kv Switchgear 140 Area 4kv Room - AB Transformer TR21A to 600Vac Bus 21A 2-T21A10 4160Vac Auxiliary 609 4kv Switchgear 140 Supply Breaker Area AB Emergency Diesel 4kv Room - AB 2-T21A11 Generator to 4kv Bus T21A Supply 4160Vac Auxiliary 609 4kv Switchgear 140 Breaker Area Unit 2

UFSAR Revision 31.0 INDIANA MICHIGAN POWER Revised: 27.0 Table: 14.4.2-1 D. C. COOK NUCLEAR PLANT Part 5 of 5 UPDATED FINAL SAFETY ANALYSIS REPORT Page: 9 of 29 Equipment Required to Shutdown Reactor (Unit 2)

(For High Energy Pipe Ruptures Outside the Containment)

Equip Id Equipment Description System Building Elev Room Rm#

4kv Room - AB 2-T21A12 Circuit Breaker From 69kv to Bus T21A 4160Vac Auxiliary 609 4kv Switchgear 140 Area 4kv Room - AB West Motor Driven Aux Feedwater Pump 2-T21A2 4160Vac Auxiliary 609 4kv Switchgear 140 PP-3W Supply Breaker Area 4kv Room - AB West Residual Heat Removal Pump 2-T21A4 4160Vac Auxiliary 609 4kv Switchgear 140 PP-35W Supply Breaker Area 4kv Room - AB West Essential Service Water 2-T21A5 4160Vac Auxiliary 609 4kv Switchgear 140 Pump PP-7W Supply Breaker Area 4kv Room - AB West Component Cooling Water 2-T21A7 4160Vac Auxiliary 609 4kv Switchgear 140 Pump PP-10W Supply Breaker Area 4kv Room - AB West Centrifugal Charging Pump 2-T21A8 4160Vac Auxiliary 609 4kv Switchgear 140 PP-50W Supply Breaker Area Unit 2

UFSAR Revision 31.0 INDIANA MICHIGAN POWER Revised: 27.0 Table: 14.4.2-1 D. C. COOK NUCLEAR PLANT Part 5 of 5 UPDATED FINAL SAFETY ANALYSIS REPORT Page: 10 of 29 Equipment Required to Shutdown Reactor (Unit 2)

(For High Energy Pipe Ruptures Outside the Containment)

Equip Id Equipment Description System Building Elev Room Rm#

4kv Room - AB 2-T21A9 4kv Bus 2A to Bus T21A Tie Breaker 4160Vac Auxiliary 609 4kv Switchgear 140 Area 4kv Room - AB 2-T21B 4kv Bus T21B Switchgear 4160Vac Auxiliary 609 4kv Switchgear 140 Area 4kv Room - AB 2-T21B1 4kv Bus 2B to 4kv Bus T21B Tie Breaker 4160Vac Auxiliary 609 4kv Switchgear 140 Area 4kv Room - AB Circuit Breaker From 69kv Bus to Bus 2-T21B2 4160Vac Auxiliary 609 4kv Switchgear 140 T21B Area AB Emergency Diesel 4kv Room - AB 2-T21B4 Generator to 4kv Bus T21B Supply 4160Vac Auxiliary 609 4kv Switchgear 140 Breaker Area 4kv Room - CD 2-T21C 4kv Bus T21C Switchgear 4160Vac Auxiliary 609 4kv Switchgear 206 Area Unit 2

UFSAR Revision 31.0 INDIANA MICHIGAN POWER Revised: 27.0 Table: 14.4.2-1 D. C. COOK NUCLEAR PLANT Part 5 of 5 UPDATED FINAL SAFETY ANALYSIS REPORT Page: 11 of 29 Equipment Required to Shutdown Reactor (Unit 2)

(For High Energy Pipe Ruptures Outside the Containment)

Equip Id Equipment Description System Building Elev Room Rm#

4kv Room - CD 2-T21C1 4kv Bus 2c to 4kv Bus T21C Tie Breaker 4160Vac Auxiliary 609 4kv Switchgear 206 Area 4kv Room - CD Circuit Breaker - 4kv From 69kv to Bus 2-T21C2 4160Vac Auxiliary 609 4kv Switchgear 206 T21C Area CD Emergency Diesel 4kv Room - CD 2-T21C3 Generator to 4kv Bus T21C Supply 4160Vac Auxiliary 609 4kv Switchgear 206 Breaker Area 4kv Room - CD 2-T21D 4kv Bus T21D Switchgear 4160Vac Auxiliary 609 4kv Switchgear 206 Area 4kv Room - CD 4kv Emergency Power Bus EP to 4kv Bus 2-T21D1 4160Vac Auxiliary 609 4kv Switchgear 206 T21D Supply Breaker Area 4kv Room - CD East Essential Service Water 2-T21D10 4160Vac Auxiliary 609 4kv Switchgear 206 Pump PP-7E Supply Breaker Area Unit 2

UFSAR Revision 31.0 INDIANA MICHIGAN POWER Revised: 27.0 Table: 14.4.2-1 D. C. COOK NUCLEAR PLANT Part 5 of 5 UPDATED FINAL SAFETY ANALYSIS REPORT Page: 12 of 29 Equipment Required to Shutdown Reactor (Unit 2)

(For High Energy Pipe Ruptures Outside the Containment)

Equip Id Equipment Description System Building Elev Room Rm#

4kv Room - CD East Motor Driven Auxiliary Feedwater 2-T21D11 4160Vac Auxiliary 609 4kv Switchgear 206 Pump PP-3E Supply Breaker Area 4kv Room - CD 2-T21D12 4kv Bus 2d to 4kv Bus T21D Tie Breaker 4160Vac Auxiliary 609 4kv Switchgear 206 Area 4kv Room - CD Transformer TR21D to 600Vac Bus 21D 2-T21D2 4160Vac Auxiliary 609 4kv Switchgear 206 Supply Breaker Area 4kv Room - CD East Component Cooling Water Pump 2-T21D3 4160Vac Auxiliary 609 4kv Switchgear 206 PP-10E Supply Breaker Area 4kv Room - CD 2-T21D6 East RHR Pump PP-35E Supply Breaker 4160Vac Auxiliary 609 4kv Switchgear 206 Area 4kv Room - CD East Centrifugal Charging 2-T21D7 4160Vac Auxiliary 609 4kv Switchgear 206 Pump PP-50e Supply Breaker Area Unit 2

UFSAR Revision 31.0 INDIANA MICHIGAN POWER Revised: 27.0 Table: 14.4.2-1 D. C. COOK NUCLEAR PLANT Part 5 of 5 UPDATED FINAL SAFETY ANALYSIS REPORT Page: 13 of 29 Equipment Required to Shutdown Reactor (Unit 2)

(For High Energy Pipe Ruptures Outside the Containment)

Equip Id Equipment Description System Building Elev Room Rm#

CD Emergency Diesel 4kv Room - CD 2-T21D8 Generator to 4kv Bus T21D Supply 4160Vac Auxiliary 609 4kv Switchgear 206 Breaker Area AB BATT Equip 2-TDAB 250 Vdc Train 'B' Transfer Cabinet 250Vdc Auxiliary 609 200 Area CD BATT Equip 2-TDCD 250 Vdc Train 'A' Transfer Cabinet 250Vdc Auxiliary 626 201 Area 2-TK-11 Boron Injection Tank Boron Injection Auxiliary 612 BIT Room 16 Lower Pressurizer Train 'B' Pressure Relief Valve 2-TK-253-1 Control Air Containment 625 Containment, 62 NRV-152 Reserve Control Air Tank Quadrant #3 Lower Pressurizer Train 'A' Pressure Relief Valve 2-TK-253-2 Control Air Containment 625 Containment, 62 NRV-153 Reserve Control Air Tank Quadrant #3 Upper Pressurizer Train 'B' Pressure Relief Valve 2-TK-253-3 Control Air Containment 650 Containment, 86 NRV-152 Emergency Air Tank Quadrant #4 Unit 2

UFSAR Revision 31.0 INDIANA MICHIGAN POWER Revised: 27.0 Table: 14.4.2-1 D. C. COOK NUCLEAR PLANT Part 5 of 5 UPDATED FINAL SAFETY ANALYSIS REPORT Page: 14 of 29 Equipment Required to Shutdown Reactor (Unit 2)

(For High Energy Pipe Ruptures Outside the Containment)

Equip Id Equipment Description System Building Elev Room Rm#

Upper Pressurizer Train 'A' Pressure Relief Valve 2-TK-253-4 Control Air Containment 650 Containment, 86 NRV-153 Emergency Air Tank Quadrant #4 Condensate Condensate 2-TK-32 Condensate Storage Tank Storage Tank Grounds 609 Storage Tank 20 Supply Area 2-TK-33 Refueling Water Storage Tank RWST Supply Grounds 609 RWST Area 21 Component 2-TK-37 Component Cooling Water Surge Tank Auxiliary 650 650 Hallway 650 Cooling Water Control Room Air Conditioning North Control Room Control Rm A/C 2-TK-76N Auxiliary 650 129 Chill Water Expansion Tank Ventilation Room Control Room Air Conditioning South Control Room Control Rm A/C 2-TK-76S Auxiliary 650 129 Chill Water Expansion Tank Ventilation Room 4kv Room -

2-TR21A 600v Bus 21A Supply Transformer 600Vac Auxiliary 609 600v Switchgear 204 Area Unit 2

UFSAR Revision 31.0 INDIANA MICHIGAN POWER Revised: 27.0 Table: 14.4.2-1 D. C. COOK NUCLEAR PLANT Part 5 of 5 UPDATED FINAL SAFETY ANALYSIS REPORT Page: 15 of 29 Equipment Required to Shutdown Reactor (Unit 2)

(For High Energy Pipe Ruptures Outside the Containment)

Equip Id Equipment Description System Building Elev Room Rm#

4kv Room -

2-TR21B 600v Bus 21B Supply Transformer 600Vac Auxiliary 609 600v Switchgear 204 Area 4kv Room - CD 2-TR21C 600v Bus 21C Supply Transformer 600Vac Auxiliary 609 4kv Switchgear 206 Area 4kv Room -

2-TR21D 600v Bus 21D Supply Transformer 600Vac Auxiliary 609 600v Switchgear 204 Area 120/208Vac Auxiliary Feedwater Misc Safety 2-TR-AFW 120/208Vac Distribution Panel AFW Auxiliary 587 CD EDG Room 122 Related Power Supply Transformer Distribution 120/208Vac 120/208Vac Emergency Local Shutdown Misc Safety 2-TR-ELSC Auxiliary 587 AB EDG Room 121 Distribution Transformer Related Power Distribution Unit 2

UFSAR Revision 31.0 INDIANA MICHIGAN POWER Revised: 27.0 Table: 14.4.2-1 D. C. COOK NUCLEAR PLANT Part 5 of 5 UPDATED FINAL SAFETY ANALYSIS REPORT Page: 16 of 29 Equipment Required to Shutdown Reactor (Unit 2)

(For High Energy Pipe Ruptures Outside the Containment)

Equip Id Equipment Description System Building Elev Room Rm#

2-VDAB-1 250Vdc Valve Distribution Panel VDAB-1 250Vdc Auxiliary 633 Control Room 123 2-VDAB-2 250Vdc Valve Distribution Panel VDAB-2 250Vdc Auxiliary 633 Control Room 123 2-VDCD-1 250Vdc Valve Distribution Panel VDCD-1 250Vdc Auxiliary 633 Control Room 123 2-VDCD-2 250Vdc Valve Distribution Panel VDCD-2 250Vdc Auxiliary 633 Control Room 123 Control Room Ventilation Control Room Control Room 2-VRV-315 Unit HV-ACRA-1 Chill Water Auxiliary 650 129 Ventilation A/C Room Inlet/Bypass Valve Control Room Ventilation Control Room Control Room 2-VRV-325 Unit HV-ACRA-2 Chill Water Auxiliary 650 129 Ventilation A/C Room Inlet/Bypass Valve East Motor Driven Auxiliary Feedwater Turbine East MDAFP 2-VTS-201 Pump Room Cooler 2- HV-AFP-EAC Building Turbine 591 50 Room Temperature Switch Ventilation Unit 2

UFSAR Revision 31.0 INDIANA MICHIGAN POWER Revised: 27.0 Table: 14.4.2-1 D. C. COOK NUCLEAR PLANT Part 5 of 5 UPDATED FINAL SAFETY ANALYSIS REPORT Page: 17 of 29 Equipment Required to Shutdown Reactor (Unit 2)

(For High Energy Pipe Ruptures Outside the Containment)

Equip Id Equipment Description System Building Elev Room Rm#

Turbine Driven Auxiliary Feed Pump Turbine 2-VTS-203 Room Cooler 2- HV-AFP-T1AC Building Turbine 591 TDAFP Room 49 Temperature Switch Ventilation Turbine Driven Auxiliary Feed Pump Turbine 2-VTS-204 Room Cooler 2-HV-AFP-T2AC Building Turbine 591 TDAFP Room 49 Temperature Switch Ventilation West Motor Driven Auxiliary Feedwater Turbine West MDAFP 2-VTS-206 Pump Room Cooler 2-HV-AFP-WAC Building Turbine 591 51 Room Temperature Switch Ventilation Emergency AB Emergency Diesel Diesel Generator 2-VTS-340 Generator Room Ventilation Supply Fan Grounds 609 RWST Area 21 Room HV-DGS-2 Outside Air Thermostat Ventilation Emergency AB Emergency Diesel Diesel Generator 2-VTS-341 Generator Room Ventilation Fans HV- Auxiliary 587 AB EDG Room 121 Room DGX-2 Thermostat Ventilation Unit 2

UFSAR Revision 31.0 INDIANA MICHIGAN POWER Revised: 27.0 Table: 14.4.2-1 D. C. COOK NUCLEAR PLANT Part 5 of 5 UPDATED FINAL SAFETY ANALYSIS REPORT Page: 18 of 29 Equipment Required to Shutdown Reactor (Unit 2)

(For High Energy Pipe Ruptures Outside the Containment)

Equip Id Equipment Description System Building Elev Room Rm#

Emergency CD Emergency Diesel Reactor Cable Diesel Generator 2-VTS-345 Generator Room Ventilation Supply Fan Auxiliary 596 Tunnel, 26 Room HV-DGS-1 Outside Air Thermostat Quadrant #3 Ventilation Emergency CD Emergency Diesel Diesel Generator 2-VTS-346 Generator Room Ventilation Exhaust Fan Auxiliary 587 CD EDG Room 122 Room HV-DGX-1 Thermostat Ventilation Control Rod Drive Equip Room and Inv ELEC. SWGR.

2-VTS-350 Area Vent North Supply Fan HV-SGRS-1a Auxiliary 609 Inverter Area 202 Ventilation Temperature Switch Control Rod Control Rod Drive Equip Room and Inv ELEC. SWGR. Drive 2-VTS-351 Area Vent North Supply Fan HV-SGRS-1a Auxiliary 609 203 Ventilation Equipment Temperature Switch Room 4kv Room 600 Volt Switchgear Xfrms 4kv Room -

ELEC. SWGR.

2-VTS-352 TR21B and TR21D Area Vent Supply Fan Auxiliary 609 600v Switchgear 204 Ventilation HV-SGRS-7 Temperature Switch Area Unit 2

UFSAR Revision 31.0 INDIANA MICHIGAN POWER Revised: 27.0 Table: 14.4.2-1 D. C. COOK NUCLEAR PLANT Part 5 of 5 UPDATED FINAL SAFETY ANALYSIS REPORT Page: 19 of 29 Equipment Required to Shutdown Reactor (Unit 2)

(For High Energy Pipe Ruptures Outside the Containment)

Equip Id Equipment Description System Building Elev Room Rm#

600Vac Motor Control Center Mezzanine ELEC. SWGR. 4kv Room -

2-VTS-353 Area Vent Supply Fan HV-SGRS-9 Auxiliary 613 205 Ventilation Mezzanine Area Temperature Switch Ctrl Rod Drv Equip Room and Inv Area ELEC. SWGR.

2-VTS-354 Vent Outside Air Inlet Damper HV-Sgr- Auxiliary 609 Inverter Area 202 Ventilation MD-2 Temperature Switch Ctrl Rod Drive Equip Room and Inv Area ELEC. SWGR.

2-VTS-355 Vent Recirc Air Inlet Damper HV-Sgr- Auxiliary 609 Inverter Area 202 Ventilation MD-1 Temperature Switch Crd Equipment Room and Inverter Area ELEC. SWGR.

2-VTS-356 Ventilation North Supply Fan HV-SGRS- Auxiliary 609 Inverter Area 202 Ventilation 4A Temp Switch Control Rod Ctrl Rod Drive Equip Room and Inv Area ELEC. SWGR. Drive 2-VTS-357 Ventilation South Supply Fan HV-SGRS- Auxiliary 609 203 Ventilation Equipment 4A Temperature Switch Room Unit 2 East ESW Pump Room East ESW Pump 2-VTS-702 ESW Ventilation Screenhouse 591 135 Temperature Switch Room Unit 2

UFSAR Revision 31.0 INDIANA MICHIGAN POWER Revised: 27.0 Table: 14.4.2-1 D. C. COOK NUCLEAR PLANT Part 5 of 5 UPDATED FINAL SAFETY ANALYSIS REPORT Page: 20 of 29 Equipment Required to Shutdown Reactor (Unit 2)

(For High Energy Pipe Ruptures Outside the Containment)

Equip Id Equipment Description System Building Elev Room Rm#

Unit 2 West ESW Pump Room West ESW 2-VTS-704 ESW Ventilation Screenhouse 591 136 Temperature Switch Pump Room 4kv Room AB 4kv Switchgear Area 4kv Room - AB ELEC. SWGR.

2-VTS-802 Ventilation Supply Fan HV-SGRS-2 Auxiliary 609 4kv Switchgear 140 Ventilation Thermal Sensor Area 4kv Room CD 4kv Switchgear Area 4kv Room - CD ELEC. SWGR.

2-VTS-803 Ventilation Supply Fan HV-SGRS-3 Auxiliary 609 4kv Switchgear 206 Ventilation Thermal Sensor Area 4kv Room 600v SWGR Xfmrs TR21B and ELEC. SWGR. 4kv Room -

2-VTS-805 TR21D Area Vent Supply Fan HV-SGRS- Auxiliary 613 205 Ventilation Mezzanine Area 7 Temp Switch Thermal Sensor 4kv Room 600v SWGR Xfmrs TR21A and 4kv Room -

ELEC. SWGR.

2-VTS-808 TR21C Area Vent Supply Fan HV-SGRS- Auxiliary 609 600v Switchgear 204 Ventilation 8 Temp Switch Temp Switch Area East Essential Service Water Supply Essential Service ESW Pipe 2-WFA-702 Turbine 569 131 Header Flow Transmitter Water Tunnel Unit 2

UFSAR Revision 31.0 INDIANA MICHIGAN POWER Revised: 27.0 Table: 14.4.2-1 D. C. COOK NUCLEAR PLANT Part 5 of 5 UPDATED FINAL SAFETY ANALYSIS REPORT Page: 21 of 29 Equipment Required to Shutdown Reactor (Unit 2)

(For High Energy Pipe Ruptures Outside the Containment)

Equip Id Equipment Description System Building Elev Room Rm#

West Essential Service Water Supply Essential Service ESW Pipe 2-WFA-706 Turbine 569 131 Header Flow Transmitter Water Tunnel East Essential Service Water Essential Service East ESW Pump 2-WMO-703 Screenhouse 591 135 Pump PP-7E Discharge Shutoff Valve Water Room West Essential Service Water Essential Service West ESW 2-WMO-704 Screenhouse 591 136 Pump PP-7W Discharge Shutoff Valve Water Pump Room West Essential Service Water Essential Service ESW Pipe 2-WMO-706 Supply Header Crosstie to Unit 1 Shutoff Turbine 569 131 Water Tunnel Valve East Essential Service Water Essential Service ESW Pipe 2-WMO-708 Supply Header Crosstie to Unit 1 Shutoff Turbine 569 131 Water Tunnel Valve East CS Hx HE-18E ESW Inlet Shutoff Essential Service 2-WMO-712 Auxiliary 633 633 Hallway 633 Valve Water Essential Service 2-WMO-716 West CS Hx ESW Inlet Shutoff Valve Auxiliary 633 633 Hallway 633 Water Unit 2

UFSAR Revision 31.0 INDIANA MICHIGAN POWER Revised: 27.0 Table: 14.4.2-1 D. C. COOK NUCLEAR PLANT Part 5 of 5 UPDATED FINAL SAFETY ANALYSIS REPORT Page: 22 of 29 Equipment Required to Shutdown Reactor (Unit 2)

(For High Energy Pipe Ruptures Outside the Containment)

Equip Id Equipment Description System Building Elev Room Rm#

West Essential Service Water CD EDG Room Essential Service 2-WMO-722-AB Supply Header to AB Emergency Diesel Auxiliary 587 North Pipe 171 Water Heat Exchangers Shutoff Valve Tunnel East Essential Service Water CD EDG Room Essential Service 2-WMO-724-AB Supply Header to AB Emergency Diesel Auxiliary 587 North Pipe 171 Water Heat Exchangers Shutoff Valve Tunnel East Essential Service Water CD EDG Room Essential Service 2-WMO-726-CD Supply Header to CD Emergency Diesel Auxiliary 587 North Pipe 171 Water Heat Exchangers Shutoff Valve Tunnel West Essential Service Water CD EDG Room Essential Service 2-WMO-728-CD Supply Header to CD Emergency Diesel Auxiliary 587 North Pipe 171 Water Heat Exchangers Shutoff Valve Tunnel East Component Cooling Water Essential Service 2-WMO-732 Heat Exchanger HE-15E Essential Service Auxiliary 609 609 Hallway 609 Water Water Inlet Shutoff Valve East Component Cooling Water Essential Service 2-WMO-734 Heat Exchanger HE-15E Essential Service Auxiliary 609 609 Hallway 609 Water Water Outlet Shutoff Valve Unit 2

UFSAR Revision 31.0 INDIANA MICHIGAN POWER Revised: 27.0 Table: 14.4.2-1 D. C. COOK NUCLEAR PLANT Part 5 of 5 UPDATED FINAL SAFETY ANALYSIS REPORT Page: 23 of 29 Equipment Required to Shutdown Reactor (Unit 2)

(For High Energy Pipe Ruptures Outside the Containment)

Equip Id Equipment Description System Building Elev Room Rm#

West Component Cooling Water Essential Service 2-WMO-736 Heat Exchanger Essential Service Water Auxiliary 609 609 Hallway 609 Water Inlet Shutoff Valve West Component Cooling Water Essential Service 2-WMO-738 Heat Exchanger Essential Service Water Auxiliary 609 609 Hallway 609 Water Outlet Shutoff Valve West Essential Service Water Essential Service ESW Pipe 2-WPI-706 Supply Header Pressure Indicator Turbine 569 131 Water Tunnel Transmitter East Essential Service Water Essential Service ESW Pipe 2-WPI-708 Supply Header Pressure Indicator Turbine 569 131 Water Tunnel Transmitter East Essential Service Water Essential Service ESW Pipe 2-WPS-702 Turbine 569 131 Supply Header Pressure Switch Water Tunnel Unit 2

UFSAR Revision 31.0 INDIANA MICHIGAN POWER Revised: 27.0 Table: 14.4.2-1 D. C. COOK NUCLEAR PLANT Part 5 of 5 UPDATED FINAL SAFETY ANALYSIS REPORT Page: 24 of 29 Equipment Required to Shutdown Reactor (Unit 2)

(For High Energy Pipe Ruptures Outside the Containment)

Equip Id Equipment Description System Building Elev Room Rm#

West Essential Service Water Essential Service ESW Pipe 2-WPS-706 Turbine 569 131 Supply Header Pressure Switch Water Tunnel ESW from CRAC N Lqd Chiller 2-HV- Essential Service Control Rm A/C 2-WRV-711-1N Auxiliary 650 129 ACR-1 Cndsr Wtr Reg Vlv (Ckt 1) Water Room ESW from CRAC N Lqd Chiller 2-HV- Essential Service Control Rm A/C 2-WRV-711-2N Auxiliary 650 129 ACR-1 Cndsr Wtr Reg Vlv (Ckt 2) Water Room ESW from CRAC S Lqd Chiller 2-HV- Essential Service Control Rm A/C 2-WRV-712-1S Auxiliary 650 129 ACR-2 Cndsr Wtr Reg Vlv (Ckt 1) Water Room ESW from CRAC S Lqd Chiller 2-HV- Essential Service Control Rm A/C 2-WRV-712-2S Auxiliary 650 129 ACR-2 Cndsr Wtr Reg Vlv (Ckt 2) Water Room CD Emergency Diesel Essential Service 2-WRV-722-CD North Combustion Air Aftercooler HE Auxiliary 587 CD EDG Room 122 Water CDn ESW Inlet/Bypass Valve CD Emergency Diesel Essential Service 2-WRV-724-CD South Combustion Air Aftercooler HE Auxiliary 587 CD EDG Room 122 Water CDS ESW Inlet/Bypass Valve Unit 2

UFSAR Revision 31.0 INDIANA MICHIGAN POWER Revised: 27.0 Table: 14.4.2-1 D. C. COOK NUCLEAR PLANT Part 5 of 5 UPDATED FINAL SAFETY ANALYSIS REPORT Page: 25 of 29 Equipment Required to Shutdown Reactor (Unit 2)

(For High Energy Pipe Ruptures Outside the Containment)

Equip Id Equipment Description System Building Elev Room Rm#

AB Emergency Diesel Essential Service 2-WRV-726-AB North Combustion Air Aftercooler HE Auxiliary 587 AB EDG Room 121 Water ABN ESW Inlet/Bypass Valve AB Emergency Diesel Essential Service 2-WRV-728-AB South Combustion Air Aftercooler HE Auxiliary 587 AB EDG Room 121 Water ABS ESW Inlet/Bypass Valve Diesel Combustion Air/AB Front Bank Air Diesel 2-XPS-300 Auxiliary 587 AB EDG Room 121 Chest Extreme High Pressure Switch Combustion Air Diesel Combustion Air/CD Front Bank Air Diesel 2-XPS-305 Auxiliary 587 CD EDG Room 122 Chest Extreme High Pressure Switch Combustion Air Upper Backup Air to 2-NRV-152 2-XRV-152 Control Air Containment 650 Containment, 86 Pressure Regulator Valve Quadrant #4 Upper Backup Air to 2-NRV-153 2-XRV-153 Control Air Containment 650 Containment, 86 Pressure Regulator Valve Quadrant #4 Unit 2

UFSAR Revision 31.0 INDIANA MICHIGAN POWER Revised: 27.0 Table: 14.4.2-1 D. C. COOK NUCLEAR PLANT Part 5 of 5 UPDATED FINAL SAFETY ANALYSIS REPORT Page: 26 of 29 Equipment Required to Shutdown Reactor (Unit 2)

(For High Energy Pipe Ruptures Outside the Containment)

Equip Id Equipment Description System Building Elev Room Rm#

Upper Backup Air to 2-NRV-152 2-XRV-154 Control Air Containment 650 Containment, 86 Low Pressure Trip Valve Quadrant #4 Upper Backup Air to 2-NRV-152 2-XRV-155 Control Air Containment 650 Containment, 86 Positive Air Shutoff Valve Quadrant #4 Upper Backup Air to 2-NRV-153 2-XRV-156 Control Air Containment 650 Containment, 86 Low Pressure Trip Valve Quadrant #4 Upper Backup Air to 2-NRV-153 2-XRV-157 Control Air Containment 650 Containment, 86 Positive Air Shutoff Valve Quadrant #4 AB Emergency Diesel Diesel Starting 2-XRV-220 Auxiliary 587 AB EDG Room 121 Starting Air Jet Assist Control Valve Air AB Emergency Diesel Diesel Starting 2-XRV-221 Auxiliary 587 AB EDG Room 121 Front Bank Starting Air Shutoff Valve Air Unit 2

UFSAR Revision 31.0 INDIANA MICHIGAN POWER Revised: 27.0 Table: 14.4.2-1 D. C. COOK NUCLEAR PLANT Part 5 of 5 UPDATED FINAL SAFETY ANALYSIS REPORT Page: 27 of 29 Equipment Required to Shutdown Reactor (Unit 2)

(For High Energy Pipe Ruptures Outside the Containment)

Equip Id Equipment Description System Building Elev Room Rm#

AB Emergency Diesel Diesel Starting 2-XRV-222 Auxiliary 587 AB EDG Room 121 Rear Bank Starting Air Shutoff Valve Air AB Emergency Diesel Diesel Starting 2-XRV-223 Starting Air to Turbocharger Pressure Auxiliary 587 AB EDG Room 121 Air Reducing Valve CD Emergency Diesel Diesel Starting 2-XRV-225 Auxiliary 587 AB EDG Room 121 Starting Air Jet Assist Control Valve Air CD Emergency Diesel Diesel Starting 2-XRV-226 Auxiliary 587 AB EDG Room 121 Front Bank Starting Air Shutoff Valve Air CD Emergency Diesel Diesel Starting 2-XRV-227 Auxiliary 587 CD EDG Room 122 Rear Bank Starting Air Shutoff Valve Air CD Emergency Diesel Diesel Starting 2-XRV-228 Starting Air to Turbocharger Pressure Auxiliary 587 CD EDG Room 122 Air Reducing Valve AB Emergency Diesel Diesel Starting 2-XRV-231 Starting Air to Control Air Dryer #1 Auxiliary 587 AB EDG Room 121 Air Pressure Reducing Valve Unit 2

UFSAR Revision 31.0 INDIANA MICHIGAN POWER Revised: 27.0 Table: 14.4.2-1 D. C. COOK NUCLEAR PLANT Part 5 of 5 UPDATED FINAL SAFETY ANALYSIS REPORT Page: 28 of 29 Equipment Required to Shutdown Reactor (Unit 2)

(For High Energy Pipe Ruptures Outside the Containment)

Equip Id Equipment Description System Building Elev Room Rm#

AB Emergency Diesel Diesel Starting 2-XRV-232 Starting Air to Control Air Dryer #2 Auxiliary 587 AB EDG Room 121 Air Pressure Reducing Valve CD Emergency Diesel Diesel Starting 2-XRV-236 Starting Air to Control Air Dryer #1 Auxiliary 587 CD EDG Room 122 Air Pressure Reducing Valve CD Emergency Diesel Diesel Starting 2-XRV-237 Starting Air to Control Air Dryer #2 Auxiliary 587 CD EDG Room 122 Air Pressure Reducing Valve 2-XTC-301 and 2-XTC-302 Diesel Control 2-XRV-240 Auxiliary 587 AB EDG Room 121 Control Air Pressure Reducing Valve (AB) Air 2-XTC-306 and 2-XTC-307 Diesel Control 2-XRV-245 Auxiliary 587 CD EDG Room 122 Control Air Pressure Reducing Valve (CD) Air Pressurizer Train 'B' Pressure Relief Valve Upper 2-XRV-RACK-152 NRV-152 Valve Rack Emergency Air Control Air Containment 652 Containment, 82 Pressure Regulator Quadrant #4 Unit 2

UFSAR Revision 31.0 INDIANA MICHIGAN POWER Revised: 27.0 Table: 14.4.2-1 D. C. COOK NUCLEAR PLANT Part 5 of 5 UPDATED FINAL SAFETY ANALYSIS REPORT Page: 29 of 29 Equipment Required to Shutdown Reactor (Unit 2)

(For High Energy Pipe Ruptures Outside the Containment)

Equip Id Equipment Description System Building Elev Room Rm#

Pressurizer Train 'A' Pressure Relief Valve Upper 2-XRV-RACK-153 NRV-153 Valve Rack Emergency Air Control Air Containment 652 Containment, 82 Pressure Regulator Quadrant #4 East Motor East Motor Driven Auxiliary Feed Pump Driven Auxiliary 2-XSO-255 AFW Turbine 591 50 Test Valve Feed Pump Room West Motor West Motor Driven Auxiliary Feed Pump Driven Auxiliary 2-XSO-345 AFW Turbine 591 51 Test Valve Feed Pump Room Pressurizer Pressurizer Train 'B' Pressure Relief Valve 2-XSO-505 Control Air Containment 652 Enclosure, 81 NRV-152 Control Solenoid Interior Pressurizer Pressurizer Train 'A' Pressure Relief Valve 2-XSO-507 Control Air Containment 652 Enclosure, 81 NRV-153 Control Solenoid Interior Unit 2

UFSAR Revision 31.0 INDIANA MICHIGAN POWER Revision: 16.4 D. C. COOK NUCLEAR PLANT Table: 14.4.2-2 UPDATED FINAL SAFETYANALYSIS REPORT Page: 1 of 1 OTHER HIGH ENERGY SYSTEMS/LINES System Sampling System Steam Generator Sample Lines Steam Generator Blowdown Sample Lines Pressurizer Sample Lines Reactor Coolant System Sample Lines System From To Bleed Steam Turbine Heater 6 Turbine Heater 6A Turbine Heater 6B Blowdown Control Valves Seat Drains Condensate Heater Bypass Feed Pump Heater 2A Heater 3A Heater 2B Heater 3B Heater 3A Heater 4A Heater 3B Heater 4B Heater 4A Feed Pump Heater 4B Feed Pump Heater 4A & 4B Feed Pump Heater 4A & 4B Feed Pump E Reheater Coil Drain Moisture Separator Reheater Drain Tank Reheater Coil Drain Reheater Drain Tank Heater 6A UNIT 2

UFSAR Revision 31.0 INDIANA AND MICHIGAN POWER Revised: 27.0 D. C. COOK NUCLEAR PLANT Table:14.4.2-3A UPDATED FINAL SAFETY ANALYSIS REPORT Page: 1 of 1 Peak Environmental Qualification Conditions for LOCA, MSLB, and Feedwater Line Break Inside Containment LOCA Location Temperature (ºF) Pressure (psig)

Upper Compartment 160 1 11.6 2 Lower Compartment 235 3 11.62 Instrument and F/A Room 235 4,3 13.9 5 MSLB and Feedwater Line Break Location Temperature (ºF) Pressure (psig)

Upper Compartment 135 (U1)6, 128 (U2) 6 20.85 Lower Compartment 325 7 20.85 1

UFSAR Figure 14.3.4-7 2

UFSAR Figure 14.3.4-6A 3

UFSAR Figure 14.3.4-8 4

Deleted 5

UFSAR Table 14.3.4-40 reports this value calculated for the Steamline Break in the Steam Generator Doghouse.

The Steam Generator Doghouse peak pressure is a bounding value for Upper and Lower Containment.

6 UFSAR Figure 14.3.4-11 (Unit 1) and Figure 14.3.4-11A (Unit 2) 7 UFSAR Figure 14.3.4-12 (Unit 1) and Figure 14.3.4-12B (Unit 2)

Unit 2

UFSAR Revision 31.0 INDIANA AND MICHIGAN POWER Revision: 22 D. C. COOK NUCLEAR PLANT Table: 14.4.2-3B UPDATED FINAL SAFETY ANALYSIS REPORT Page: 1 of 1 AIRBORNE SOURCE TERM DOSES AND DOSE RATES Containment Centerline Dose Rates and Doses1 Time Gamma Dose Beta Dose Rate Total Dose Rate Gamma Dose Beta Dose Total Dose Rate [rad/hr[ [rad/hr[ [rad/hr] [rad] [rad] [rad]

1 second 4.293E+06 2.028E+07 2.46E+07 5.962E+02 2.817E+03 3.41E+03 30 minutes 1.905E+06 7.674E+06 9.58E+06 1.330E+06 5.196E+06 6.53E+06 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months 1.418E+06 6.592E+06 8.01E+06 2.145E+06 8.756E+06 1.09E+07 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months 9.818E+05 4.849E+06 5.83E+06 3.319E+06 1.443E+07 1.77E+07 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months 4.013E+05 1.508E+06 1.91E+06 6.889E+06 3.046E+07 3.73E+07 1 day 2.181E+05 5.753E+05 7.93E+05 1.131E+07 4.382E+07 5.51E+07 7 days 8.274E+04 2.350E+05 3.18E+05 3.014E+07 9.492E+07 1.25E+08 30 days 4.543E+03 1.708E+04 2.16E+04 4.480E+07 1.385E+08 1.83E+08 90 days 3.484E+01 5.456E+03 5.49E+03 4.580E+07 1.487E+08 1.94E+08 180 days 2.515E+01 5.352E+03 5.38E+03 4.586E+07 1.603E+08 2.06E+08 365 days 2.431E+01 5.175E+03 5.20E+03 4.597E+07 1.837E+08 2.30E+08 Inside Containment Wall Surface Dose Rates and Doses (1)

Time Gamma Dose Beta Dose Rate Total Dose Rate Gamma Dose Beta Dose Total Dose Rate [rad/hr[ [rad/hr[ [rad/hr] [rad] [rad] [rad]

1 second 3.408E+06 2.028E+07 2.37E+07 4.734E+02 2.817E+03 3.29E+03 30 minutes 1.906E+06 7.674E+06 9.58E+06 1.205E+06 5.196E+06 6.40E+06 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months 1.499E+06 6.592E+06 8.09E+06 2.046E+06 8.756E+06 1.08E+07 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months 1.080E+06 4.849E+06 5.93E+06 3.314E+06 1.443E+07 1.77E+07 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months 4.627E+05 1.508E+06 1.97E+06 7.346E+06 3.046E+07 3.78E+07 1 day 2.259E+05 5.753E+05 8.01E+05 1.228E+07 4.382E+07 5.61E+07 7 days 6.730E+04 2.350E+05 3.02E+05 2.832E+07 9.492E+07 1.23E+08 30 days 5.276E+03 1.708E+04 2.24E+04 4.141E+07 1.385E+08 1.80E+08 90 days 3.538E+01 5.456E+03 5.49E+03 4.274E+07 1.487E+08 1.91E+08 180 days 1.313E+01 5.352E+03 5.37E+03 4.277E+07 1.603E+08 2.03E+08 365 days 1.268E+01 5.175E+03 5.19E+03 4.283E+07 1.837E+08 2.27E+08 1

Per Calculation RS-C-0046 UNIT 2

UFSAR Revision 31.0 INDIANA AND MICHIGAN POWER Revision: 22 D. C. COOK NUCLEAR PLANT Table: 14.4.2-3C UPDATED FINAL SAFETY ANALYSIS REPORT Page: 1 of 1 SUBMERGED LOWER VOLUME / CONTAINMENT SUMP DOSE RATES & DOSES1 Beta Dose Gamma Dose Total Dose Gamma Dose Beta Dose Total Dose Time Rate Rate (rad/hr) Rate (rad/hr) (rad) (rad) (rad)

(rad/hr) 1 second 1.201E+06 1.791E+05 1.38E+06 1.668E+02 2.488E+01 1.92E+02 30 minutes 9.675E+05 1.388E+05 1.11E+06 5.377E+05 7.812E+04 6.16E+05 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months 8.100E+05 1.177E+05 9.28E+05 9.799E+05 1.418E+05 1.12E+06 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months 6.118E+05 9.462E+04 7.06E+05 1.682E+06 2.467E+05 1.93E+06 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months 2.834E+05 5.775E+04 3.41E+05 4.061E+06 6.719E+05 4.73E+06 1 day 1.315E+05 3.291E+04 1.64E+05 7.072E+06 1.364E+06 8.44E+06 7 days 3.467E+04 8.429E+03 4.31E+04 1.511E+07 3.346E+06 1.85E+07 30 days 9.922E+03 3.262E+03 1.32E+04 2.527E+07 6.123E+06 3.14E+07 90 days 3.470E+03 1.753E+03 5.22E+03 3.307E+07 9.351E+06 4.24E+07 180 days 1.733E+03 1.221E+03 2.95E+03 3.838E+07 1.249E+07 5.09E+07 365 days 7.349E+02 7.538E+02 1.49E+03 4.328E+07 1.673E+07 6.00E+07 1

Per Calculation RS-C-0046 UNIT 2

UFSAR Revision 31.0 INDIANA AND MICHIGAN POWER Revision: 22 D. C. COOK NUCLEAR PLANT Table:14.4.2-3D UPDATED FINAL SAFETY ANALYSIS REPORT Page: 1 of 1 BETA DOSE FACTORS1 DOSE FROM AIRBORNE SOURCE AFTER ATTENUATION (PERCENTAGE OF DOSE PASSING THROUGH SHIELD)

Thickness of Unit Density Material (mils)

Time 10 20 30 40 50 60 70 1 second 78.68% 68.30% 60.73% 54.66% 49.58% 45.22% 41.38%

30 minutes 75.18% 64.48% 56.96% 51.04% 46.14% 41.94% 38.30%

1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months 75.37% 65.13% 57.92% 52.22% 47.48% 43.41% 39.83%

2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months 75.21% 65.41% 58.57% 53.16% 48.62% 44.71% 41.28%

8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months 70.04% 60.58% 54.41% 49.62% 45.62% 42.23% 39.24%

1 day 58.35% 48.97% 43.53% 39.50% 36.24% 33.49% 31.11%

7 days 31.56% 23.58% 20.49% 18.47% 16.88% 15.57% 14.44%

30 days 24.49% 16.73% 14.23% 12.73% 11.60% 10.68% 9.90%

90 days 24.78% 16.40% 13.60% 12.01% 10.87% 9.98% 9.24%

180 days 25.51% 16.28% 13.08% 11.34% 10.18% 9.30% 8.59%

365 days 26.67% 16.08% 12.22% 10.24% 9.03% 8.18% 7.52%

1 Per Calculation RS-C-0046 UNIT 2

UFSAR Revision 31.0 INDIANA AND MICHIGAN POWER Revision: 22 D. C. COOK NUCLEAR PLANT Table: 14.4.2-3E UPDATED FINAL SAFETY ANALYSIS REPORT Page: 1 of 1 BETA DOSE FACTORS1 DOSE FROM AIRBORNE SOURCE AFTER ATTENUATION (PERCENTAGE OF DOSE PASSING THROUGH SHIELD)

Thickness of Aluminum (mils)

Time 10 20 30 40 50 60 70 1 second 62.82% 47.77% 37.66% 30.25% 24.53% 20.03% 16.43%

30 minutes 59.01% 44.39% 34.79% 27.80% 22.49% 18.33% 15.05%

1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months 59.89% 45.77% 36.38% 29.42% 24.07% 19.84% 16.46%

2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months 60.44% 46.99% 37.93% 31.11% 25.77% 21.51% 18.05%

8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months 56.09% 44.21% 36.31% 30.30% 25.53% 21.64% 18.42%

1 day 44.98% 35.09% 28.78% 24.07% 20.33% 17.27% 14.74%

7 days 21.26% 16.33% 13.36% 11.16% 9.42% 8.00% 6.83%

30 days 14.81% 11.21% 9.15% 7.65% 6.45% 5.48% 4.68%

90 days 14.25% 10.50% 8.53% 7.12% 6.01% 5.11% 4.36%

180 days 13.81% 9.80% 7.93% 6.61% 5.58% 4.74% 4.04%

365 days 13.09% 8.65% 6.92% 5.77% 4.87% 4.14% 3.53%

1 Per Calculation RS-C-0046 UNIT 2

UFSAR Revision 31.0 INDIANA AND MICHIGAN POWER Revision: 22 D. C. COOK NUCLEAR PLANT Table: 14.4.2-3F UPDATED FINAL SAFETY ANALYSIS REPORT Page: 1 of 1 BETA DOSE FACTORS1 DOSE FROM AIRBORNE SOURCE AFTER ATTENUATION (PERCENTAGE OF DOSE PASSING THROUGH SHIELD)

Thickness of Steel (mils)

Time 10 20 30 40 50 60 70 1 second 38.44% 20.75% 11.76% 6.82% 4.01% 2.39% 1.43%

30 minutes 35.52% 19.00% 10.83% 6.41% 3.89% 2.41% 1.52%

1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months 37.10% 20.53% 12.05% 7.34% 4.59% 2.92% 1.88%

2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months 38.62% 22.20% 13.46% 8.42% 5.39% 3.50% 2.30%

8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months 36.91% 22.27% 14.05% 9.08% 5.96% 3.95% 2.64%

1 day 29.27% 17.77% 11.29% 7.33% 4.83% 3.22% 2.16%

7 days 13.58% 8.23% 5.23% 3.40% 2.24% 1.49% 1.00%

30 days 9.31% 5.64% 3.58% 2.33% 1.53% 1.02% 0.68%

90 days 8.68% 5.26% 3.34% 2.17% 1.43% 0.95% 0.64%

180 days 8.06% 4.88% 3.10% 2.01% 1.33% 0.88% 0.59%

365 days 7.05% 4.26% 2.70% 1.76% 1.16% 0.77% 0.52%

1 Per Calculation RS-C-0046 UNIT 2

UFSAR Revision 31.0 INDIANA AND MICHIGAN POWER Revision: 22 D. C. COOK NUCLEAR PLANT Table:14.4.2-3G UPDATED FINAL SAFETY ANALYSIS REPORT Page: 1 of 1 PIPES CONSIDERED IN CALCULATING OUTSIDE CONTAINMENT DOSES1 Outside Diameter Wall Thickness, System Designation 2 OD/T OD (inches) T (inches)

CC M-14 4.5 0.438 10.3 CC M-14 3.5 0.438 7.99 CC M-14 2.0 0.344 5.81 CC B-14 6.625 0.134 49.44 CC B-14 8.625 0.148 58.28 SI K-14 4.5 0.337 13.35 SI B-14 4.5 0.12 37.5 SI B-14 6.625 0.134 49.44 SI K-14 2.375 0.276 8.61 SI K-14 1.9 0.2 9.5 SI K-14 1.05 0.154 6.82 RHR G-14 14.0 0.438 31.96 RHR G-14 3.5 0.216 16.20 RHR G-14 8.625 0.322 26.79 CS E-14 10.75 0.365 29.45 CS E-14 8.625 0.322 26.79 CS E-14 6.625 0.28 23.66 CS E-14 3.5 0.216 16.20 CS E-14 1.315 0.133 9.89 CS B-14 8.625 0.148 58.28 CS G-14 12.75 0.406 31.40 CS G-14 2.375 0.154 15.42 Key:

CC - Centrifugal Charging SI - Safety Injection RHR - Residual Heat Removal CS - Containment Spray 1

AEP: NRC: 05781, Attachment 4 2

Note: Pipe designation indicates materials of construction, seismic classification, and quality level. For further information, AEPSC specifications should be consulted.

UNIT 2

UFSAR Revision 31.0 INDIANA AND MICHIGAN POWER Revision: 24.0 D. C. COOK NUCLEAR PLANT Table:14.4.2-3H UPDATED FINAL SAFETY ANALYSIS Page: 1 of 1 REPORT PEAK ENVIRONMENTAL QUALIFICATION CONDITIONS FOR HELB OUTSIDE CONTAINMENT COMPARTMENT TEMPERATURE (ºF) PRESSURE (psia)

East Main Steam Enclosure 440 18.7 West Main Steam Enclosure 485 20.6 Main Steam Accessway 347.8 18.2 Diesel Generator Pipe Tunnel 300 15.3 Turbine Driven Pump Room 298 16.7 ESW Tunnel 300 15.1 Turbine Room (Turbine Bldg. 609' Elev.) 473.8 15.45 Startup Blowdown Flashtank Room 216.5 15.2 NOTE:

Only major areas are identified in the table above.

UNIT 2

UFSAR Revision 31.0 INDIANA MICHIGAN POWER Revision: 17 D. C. COOK NUCLEAR PLANT Table: 14.4.2-5 UPDATED FINAL SAFETY ANALYSIS REPORT Page: 1 of 1 POSTULATED MAJOR HIGH ENERGY LINE BREAKS Line Size No. of Line System Description/Location Building Area (in) Breaks MS 30 2 Containment Penetrations Auxiliary ESE MS 30 2 Containment Penetrations Auxiliary WSE MS 30 2 5-way Restraint Auxiliary ESE MS 30 2 5-way Restraint Auxiliary WSE MS 4 2 At 30 in. Header Turbine Near Main Turbine MS 4 1 AFP Turbine Turbine TDAFP Room FW 14 2 Containment Penetrations Auxiliary ESE FW 14 2 Containment Penetrations Auxiliary WSE FW 20 1 Heater 6 Nozzle Turbine Heater 6 (A&B)

AFW/FW 6 2 At 14 in. Heater Auxiliary ESE AFW/FW 6 2 At 14 in. Heater Auxiliary WSE Letdown Heat CVCS-LD 2 1 Letdown Heat Exchanger Auxiliary Exchanger Room Notes:

1. Breaks in high energy systems that are not listed above are postulated to occur anywhere in the high energy portion of piping.

UNIT 2

UFSAR Revision 31.0 INDIANA MICHIGAN POWER Revision: 16.6 D. C. COOK NUCLEAR PLANT Table: 14.4.6-1 UPDATED FINAL SAFETY ANALYSIS REPORT Page: 1 of 1 WEST STEAM ENCLOSURE/MAIN STEAM ACCESSWAY VENT AREA AND VOLUME INPUTS TO TMD Vent Area Volume Element No.1 (ft2) (ft3) 1 Atmosphere Atmosphere 2 827 2919 3 875 4737 4 988 5736 5 487 6145 6 336 3900 7 530 9078 8 816 9078 9 558 9078 10 258 2033 11 507 7006 12 320 3266 1

Element numbers refer to Figures 14.4.6-1 and 14.4.6-2.

UNIT 2

UFSAR Revision 31.0 INDIANA MICHIGAN POWER Revision: 16.6 D. C. COOK NUCLEAR PLANT Table: 14.4.6-2 UPDATED FINAL SAFETY ANALYSIS REPORT Page: 1 of 1 EAST STEAM ENCLOSURE VENT AREA AND VOLUME INPUTS TO TMD Vent Area Volume Element No.1 (ft2) (ft3) 1 Atmosphere Atmosphere 2 898 4608 3 899 5102 4 880 4102 5 532 8145 6 547 7093 7 834 4041 1

Element numbers refer to Figures 14.4.6-3 and 14.4.6-4.

UNIT 2

UFSAR Revision 31.0 INDIANA MICHIGAN POWER Revision: 16.6 D. C. COOK NUCLEAR PLANT Table: 14.4.6-3 UPDATED FINAL SAFETY ANALYSIS REPORT Page: 1 of 1 MODEL PARAMETERS (WEST MAIN STEAM ENCLOSURE AND MAIN STEAM ACCESSWAY)

LARGE BREAK Volume Height Elevation Heat Slab Area Element No.1 (ft3) (ft) (ft) (ft2) 2 10600 29 633 2400 3 10600 29 633 2500 4 8400 11.5 621.5 1500 5 4500 21 600.5 3950 6 173000 20 587 3950 7 173000 20 587 1900 8 11300 18 662 1900 9 11300 18 662 1

Element numbers refer to Figure 14.4.6-5.

UNIT 2

UFSAR Revision 31.0 INDIANA MICHIGAN POWER Revision: 16.6 D. C. COOK NUCLEAR PLANT Table: 14.4.6-3a UPDATED FINAL SAFETY ANALYSIS REPORT Page: 1 of 1 MODEL PARAMETERS (WEST MAIN STEAM ENCLOSURE AND MAIN STEAM ACCESSWAY)

SMALL BREAK Volume Height Elevation Element No.1 (ft3) (ft) (ft) 2 10600 29 633 3 10600 29 633 4 8400 11.5 622 5 4500 21 601 6 173000 20 587 7 173000 20 587 8 11300 18 664 9 11300 18 664 1

Element numbers refer to Figure 14.4.6-5.

UNIT 2

UFSAR Revision 31.0 INDIANA MICHIGAN POWER Revision: 16.6 D. C. COOK NUCLEAR PLANT Table: 14.4.6-4 UPDATED FINAL SAFETY ANALYSIS REPORT Page: 1 of 1 MODEL PARAMETERS (EAST MAIN STEAM ENCLOSURE)

LARGE BREAK Volume Height Elevation Heat Slab Area Element No.1 (ft3) (ft) (ft) (ft2) 2 10600 29 633 2250 3 10600 29 633 2550 4 8100 11.5 621.5 2500 5 5800 9.5 612 4700 6 9600 16. 612 1400 7 6900 18 662 1400 8 6900 18 662 9

1 Element numbers refer to Figure 14.4.6-6.

UNIT 2

UFSAR Revision 31.0 INDIANA MICHIGAN POWER Revision: 16.6 D. C. COOK NUCLEAR PLANT Table: 14.4.6-4a UPDATED FINAL SAFETY ANALYSIS REPORT Page: 1 of 1 MODEL PARAMETERS (EAST MAIN STEAM ENCLOSURE)

SMALL BREAK Element No.1 Volume Height Elevation (ft3) (ft) (ft) 2 10600 29 633 3 10600 29 633 4 8100 11.5 622 5 5800 9.5 612 6 9600 16. 612 7 6900 18 664 8 6900 18 664 1

Element numbers refer to Figure 14.4.6-6.

UNIT 2

UFSAR Revision 31.0 INDIANA MICHIGAN POWER Revision: 21.2 D. C. COOK NUCLEAR PLANT Table: 14.4.6-5 UPDATED FINAL SAFETY ANALYSIS REPORT Page: 1 of 1 MASS AND ENERGY RELEASE FOR STEAM LINE BREAK IN MAIN STEAM ENCLOSURE LARGE BREAK Time Mass/Flow Enthalpy (sec) (lbm/sec) (Btu/lbm) 0 0 1198 0.001 1 6508 1198 0.5 6508 1198 1.5 6124 1199 4.0 5599 1201 4.5 6091 1201 7.0 6091 1201 12.5 5788 1202 13.0 1976 1202 30.0 1158 1204 40.0 994.7 1204 60.0 890.3 1203 74.0 874.9 1205 75.0 866.8 1209 85.0 644.1 1245 95.0 256.2 1276 105.0 29.1 1294 200.0 29.2 1310 400.0 34.6 1312 600.0 34.6 1311 1800.00 34.6 1311 1800.01 0 1311 3600.0 0 1311 1

Full break opening assumed in 0.001 sec.

UNIT 2

UFSAR Revision 31.0 INDIANA MICHIGAN POWER Revision: 16.6 D. C. COOK NUCLEAR PLANT Table: 14.4.6-5a UPDATED FINAL SAFETY ANALYSIS REPORT Page: 1 of 1 MASS AND ENERGY RELEASE FOR STEAM LINE BREAK IN MAIN STEAM ENCLOSURE SMALL BREAK Time Flow Enthalpy (sec) (lbm/sec) (Btu/lbm) 0.5 2102. 1196.

10.0 1832. 1199.

25.0 1645. 1201.

50.0 1575. 1202.

100.0 1568. 1202.

108.0 1568. 1202.

109.0 1673. 1201.

117.0 2057. 1197.

135.0 1823. 1200.

150.0 1642. 1202.

179.0 1453. 1203.

181.0 1447. 1204.

200.0 1410. 1208.

258.0 1099. 1238.

259.0 1089. 1239.

275.0 226.1 1281.

300.0 29.9 1296.

400.0 34.4 1297.

500.0 34.6 1298.

600.0 34.6 1299.

UNIT 2

UFSAR Revision 31.0 INDIANA MICHIGAN POWER Revision: 16.6 D. C. COOK NUCLEAR PLANT Table: 14.4.6-6 UPDATED FINAL SAFETY ANALYSIS REPORT Page: 1 of 1 FEEDWATER LINE BREAK AT THE CONTAINMENT PENETRATION (APPLICABLE TO EAST OR WEST STEAM ENCLOSURE)

Mass and Enthalpy Forward Flow m = 4400 lbm/sec n = 431 Btu/lbm Energy Flow = 1.896 x 106 Back Flow m = 6800 lbm/sec 3.713 x 106 n = 546 Btu/lbm 25 seconds Total = 5.609 x 106 (Up to 25 Seconds)

UNIT 2

UFSAR Revision 31.0 INDIANA MICHIGAN POWER Revision: 16.6 D. C. COOK NUCLEAR PLANT Table: 14.4.6-6a UPDATED FINAL SAFETY ANALYSIS REPORT Page: 1 of 2 STEAM LINE BREAK - FORWARD FLOW EAST/WEST STEAM ENCLOSURES (Pressure Response)

Time Mass Flow Energy Release (sec) 103 lb/sec 106 Btu/sec 0.0 5.55 6.62 0.1 4.15 4.94 0.2 3.05 3.64 0.4 2.95 3.52 0.6 2.90 3.46 0.8 2.78 3.31 1.0 2.75 3.28 1.5 2.67 3.19 2.0 3.45 3.38 2.5 9.50 5.26 3.0 9.42 5.21 3.5 9.38 5.19 4.0 9.33 5.16 4.5 9.28 5.13 5.0 9.23 5.10 5.5 9.16 5.07 6.0 9.10 5.04 6.5 9.03 5.01 7.0 8.95 4.97 7.5 8.86 4.93 8.0 8.80 4.91 8.5 8.70 4.86 9.0 8.58 4.81 9.5 8.46 4.76 10.0 8.33 4.70 UNIT 2

UFSAR Revision 31.0 INDIANA MICHIGAN POWER Revision: 16.6 D. C. COOK NUCLEAR PLANT Table: 14.4.6-6a UPDATED FINAL SAFETY ANALYSIS REPORT Page: 2 of 2 STEAM LINE BREAK - FORWARD FLOW EAST/WEST STEAM ENCLOSURES (Pressure Response)

Time Mass Flow Energy Release (sec) 103 lb/sec 106 Btu/sec 12.0 7.67 4.42 14.0 6.75 4.05 16.0 5.49 3.53 18.0 4.04 2.95 19.0 3.37 2.67 UNIT 2

UFSAR Revision 31.0 INDIANA MICHIGAN POWER Revision: 16.6 D. C. COOK NUCLEAR PLANT Table: 14.4.6-6b UPDATED FINAL SAFETY ANALYSIS REPORT Page: 1 of 2 EAST STEAM ENCLOSURE STEAMLINE BREAK - BACKFLOW (PRESSURE RESPONSE)

Time Mass Flow Energy Release (sec) 103 lb/sec 106 Btu/sec 0.0 7.54 8.99 0.1 5.09 6.07 0.2 4.61 5.50 0.3 4.41 5.26 0.4 4.34 5.17 0.5 4.26 5.08 0.6 4.19 4.99 0.7 4.36 5.20 0.8 4.80 5.72 0.9 4.78 5.70 1.0 4.77 5.69 1.5 4.90 5.84 2.0 5.00 5.96 2.5 4.75 5.66 3.0 4.71 5.61 3.5 4.65 5.54 4.0 4.59 5.47 4.5 4.52 5.39 5.0 4.35 5.19 5.5 4.15 4.95 6.0 3.98 4.75 6.5 3.96 4.72 7.0 4.26 4.50 UNIT 2

UFSAR Revision 31.0 INDIANA MICHIGAN POWER Revision: 16.6 D. C. COOK NUCLEAR PLANT Table: 14.4.6-6b UPDATED FINAL SAFETY ANALYSIS REPORT Page: 2 of 2 EAST STEAM ENCLOSURE STEAMLINE BREAK - BACKFLOW (PRESSURE RESPONSE)

Time Mass Flow Energy Release (sec) 103 lb/sec 106 Btu/sec 7.5 4.93 4.70 8.0 5.71 5.03 8.5 6.45 5.37 9.0 7.14 5.81 9.5 7.70 6.05 10.0 8.23 6.39 UNIT 2

UFSAR Revision 31.0 INDIANA MICHIGAN POWER Revision: 16.6 D. C. COOK NUCLEAR PLANT Table: 14.4.6-6c UPDATED FINAL SAFETY ANALYSIS REPORT Page: 1 of 2 WEST STEAM ENCLOSURE STEAMLINE BREAK - BACKFLOW (PRESSURE RESPONSE)

Time Mass Flow Energy Release (sec) 103 lb/sec 106 Btu/sec 0.0 7.54 8.99 0.1 5.09 6.07 0.2 4.61 5.50 0.3 4.41 5.26 0.4 4.30 5.13 0.5 4.58 5.46 0.6 4.97 5.92 0.7 5.09 6.07 0.8 5.11 6.09 0.9 5.13 6.11 1.0 5.07 6.04 1.5 5.29 6.31 2.0 5.11 6.10 2.5 4.96 5.91 3.0 4.93 5.88 3.5 4.81 5.77 4.0 4.68 5.58 4.5 4.59 5.47 5.0 4.53 5.40 5.5 4.65 5.16 6.0 5.28 5.17 6.5 5.90 5.55 7.0 6.46 5.78 7.5 6.88 5.93 UNIT 2

UFSAR Revision 31.0 INDIANA MICHIGAN POWER Revision: 16.6 D. C. COOK NUCLEAR PLANT Table: 14.4.6-6c UPDATED FINAL SAFETY ANALYSIS REPORT Page: 2 of 2 WEST STEAM ENCLOSURE STEAMLINE BREAK - BACKFLOW (PRESSURE RESPONSE)

Time Mass Flow Energy Release (sec) 103 lb/sec 106 Btu/sec 8.0 7.32 6.10 8.5 7.79 6.32 9.0 8.23 6.53 9.5 8.61 6.72 10.0 8.92 6.88 UNIT 2

UFSAR Revision 31.0 INDIANA MICHIGAN POWER Revision: 16.6 D. C. COOK NUCLEAR PLANT Table: 14.4.6-7 UPDATED FINAL SAFETY ANALYSIS REPORT Page: 1 of 1 FEEDWATER LINE BREAK AT THE TEE BETWEEN THE 20 INCH AND 30 INCH LINES, 20 INCH LINE RUNNING TO STEAM GENERATORS 2 AND 3 (APPLICABLE TO MAIN STEAM ACCESSWAY)

Mass and Enthalpy Forward Flow m = 9050 lbm/sec n = 431 Btu/lbm Back Flow m = 9050 lbm/sec n = 431 Btu/lbm 1.5 seconds UNIT 2

UFSAR Revision 31.0 INDIANA MICHIGAN POWER Revision: 16.6 D. C. COOK NUCLEAR PLANT Table: 14.4.6-8 UPDATED FINAL SAFETY ANALYSIS REPORT Page: 1 of 1 RELATION OF NODE CALCULATED PRESSURE TO PRESSURE CAPABILITY OF SLABS Long Term Pressure Weakest Slab Capability Area Node Number Following Anticipated for Static Differential Transient Psi 1 Pressure Psi East Steam Enclosure 2 5.5 13.4 (See Figure 14.4.6-3) 3 5.5 11.6 4 5.5 11.6 5 5.5 11.6 2 6 5.5 11.6 (2) 7 5.5 13.4 West Steam Enclosure 2 4.7 10.9 (1)

(See Figure14.4.6-1) 3 4.7 10.9 (1) 4 4.7 22.1 5 4.7 4.5 3 (W SL1) 6 4.7 26.2 11 4.7 4.5 (3) (W SL1) 12 4.7 22.1 Main Steam Accessway 7 5.8 9.3 (See Figure14.4.6-1) 8 5.3 9.3 9 5.1 9.4 10 1.0 15.7 1

Tables 14.4.6-18, -19 and -20 show results of dynamic analyses for the respective slabs.

2 Other than lightly reinforced portion panel section E-W4, which will be allowed to fail without causing any damage to equipment required to safely shutdown the plant.

3 See Section 14.4.9.

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UFSAR Revision 31.0 INDIANA MICHIGAN POWER Revision: 16.6 D. C. COOK NUCLEAR PLANT Table: 14.4.6-9 UPDATED FINAL SAFETY ANALYSIS REPORT Page: 1 of 1 PEAK PRESSURE DIFFERENTIAL MAIN STEAM LINE BREAK WEST STEAM ENCLOSURE Peak Pressure Differential Element No. 1 (psi) 1 0 2 11.9 3 (Break Location) 11.3 4 8.7 5 11.7 6 6.2 7 4.2 8 4.1 9 3.7 10 .65 11 8.8 12 7.6 1

Element numbers refer to Figure 14.4.6-1.

UNIT 2

UFSAR Revision 31.0 INDIANA MICHIGAN POWER Revision: 16.6 D. C. COOK NUCLEAR PLANT Table: 14.4.6-10 UPDATED FINAL SAFETY ANALYSIS REPORT Page: 1 of 1 PEAK DIFFERENTIAL PRESSURE FEEDWATER LINE BREAK IN WEST STEAM ENCLOSURE Peak Pressure Element No. 1 (psig) 1 0 2 4.2 3 (Break Location) 4.3 4 2.7 5 3.7 6 2.1 7 1.7 8 1.6 9 1.4 10 .3 11 3.2 12 2.6 1

Element numbers refer to Figure 14.4.6-1.

UNIT 2

UFSAR Revision 31.0 INDIANA MICHIGAN POWER Revision: 16.6 D. C. COOK NUCLEAR PLANT Table: 14.4.6-11 UPDATED FINAL SAFETY ANALYSIS REPORT Page: 1 of 1 PEAK DIFFERENTIAL PRESSURE FEEDWATER LINE BREAK IN MAIN STEAM ACCESSWAY Peak Pressure Element No. 1 (psi) 1 0 2 1.8 3 1.8 4 1.8 5 2.0 6 2.5 7 (Break Location) 5.8 8 5.3 9 5.1 10 1.0 11 2.0 12 1.8 1

Element numbers refer to Figure 14.4.6-1.

UNIT 2

UFSAR Revision 31.0 INDIANA MICHIGAN POWER Revision: 16.6 D. C. COOK NUCLEAR PLANT Table: 14.4.6-12 UPDATED FINAL SAFETY ANALYSIS REPORT Page: 1 of 1 PEAK DIFFERENTIAL PRESSURE MAIN STEAM LINE BREAK IN EAST STEAM ENCLOSURE Peak Pressure Element No. 1 (psi) 1 0 2 7.7 3 7.8 4 (Break Location) 11.8 5 8.3 6 12.0 7 11.0 1

Element numbers refer to Figure 14.4.6-3.

UNIT 2

UFSAR Revision 31.0 INDIANA MICHIGAN POWER Revision: 16.6 D. C. COOK NUCLEAR PLANT Table: 14.4.6-13 UPDATED FINAL SAFETY ANALYSIS REPORT Page: 1 of 1 PEAK DIFFERENTIAL PRESSURE FEEDWATER LINE BREAK IN EAST STEAM ENCLOSURE Peak Pressure Element No. 1 (psig) 1 0 2 2.7 3 2.8 4 (Break Location) 4.1 5 3.0 6 4.2 7 3.9 1

Element numbers refer to Figure 14.4.6-3.

UNIT 2

UFSAR Revision 31.0 INDIANA MICHIGAN POWER Revision: 16.6 D. C. COOK NUCLEAR PLANT Table: 14.4.6-14 UPDATED FINAL SAFETY ANALYSIS REPORT Page: 1 of 1 RELATION OF NODES USED IN MAIN STEAM ACCESSWAY ANALYSIS TO PANEL IDENTIFICATION PRESENTED IN TABLE 14.4.6-17 Node No. 1 Affected Slabs 7 W-SL3, W-SL4, W-WN3, W-WS7, WS9, W-W7 8 W-SL3, W-SL4, W-SL5, W-WN3, W-WS7, W-WS8, W-WS9 9 W-SL3, W-SL5, W-WN4, W-WN3, W-WS8, W-WS9, W-WS10 10 W-W8, W-W9, W-WN4, W-W10, W-W9A 1

Node numbers refer to Figure 14.4.6-1.

UNIT 2

UFSAR Revision 31.0 INDIANA MICHIGAN POWER Revision: 16.6 D. C. COOK NUCLEAR PLANT Table: 14.4.6-15 UPDATED FINAL SAFETY ANALYSIS REPORT Page: 1 of 1 PRESSURE CAPABILITY OF WALLS & SLABS AROUND MAIN STEAM LINE ENCLOSURE EAST OF CONTAINMENT

1. MATERIAL PROPERTIES

a. Concrete fc' = 3500 psi;

b. Reinforcing steel fy= 40000 psi

2. PRESSURE CAPABILITIES TABULATED

a. Are ultimate values under static conditions;

b. Do not include any other loading condition Pressure Panel ID Thickness Capability Remarks (in.)

(psi)

E-SL2 12 11.6 Punching Shear Around Col. Governs E-SL3 30 72.5 1 E-WN1 24 16.1 (1)

E-WN2 24 80.0 (1)

E-WS1 24 16.0 (1)

E-WS2 24 83.2 (1)

E-W1 24 13.4 (1)

E-W2 24 78.0 (1)

E-W3 & E-W4, both curved are solved using planar E-W3 24 11.6 (1) projections Critical Value of 4.5 PSI. Results from 1 way action of lightly reinforced portion of panel between the two E-W4 24 4.5 large openings. The side portions of the panel have capability of 86.1 (1)

See Figure 14.4.6-3 for wall and slab identification.

1 Indicates diagonal tension failure governs.

UNIT 2

UFSAR Revision 31.0 INDIANA MICHIGAN POWER Revision: 16.6 D. C. COOK NUCLEAR PLANT Table:14.4.6-15a UPDATED FINAL SAFETY ANALYSIS REPORT Page: 1 of 1 RELATION OF NODES USED IN EAST STEAM ENCLOSURE ANALYSIS TO PANEL IDENTIFICATION PRESENTED IN TABLE 14.4.6-15 Node No. 1 Affected Slabs 2 E-WS1, E-W1 3 E-WS1, E-W3 4 E-WS3, E-WN1 5 E-W1, E-WS1, E-SL2, E-W4, E-W3, E-WS2, E-W2 6 E-W3, E-W4, E-SL2, E-WN1, E-WN2, E-W1, E-W2 7 E-W1, E-WN1 1

Node numbers refer to Figure 14.4.6-3.

UNT 2

UFSAR Revision 31.0 INDIANA MICHIGAN POWER Revision: 16.6 D. C. COOK NUCLEAR PLANT Table: 14.4.6-16 UPDATED FINAL SAFETY ANALYSIS REPORT Page: 1 of 1 PRESSURE CAPABILITY OF WALLS AND SLABS AT MAIN STEAM ENCLOSURE WEST OF CONTAINMENT

1. MATERIAL PROPERTIES

a. Concrete fc' = 3500 psi;

b. Reinforcing steel fy = 40000 psi

2. PRESSURE CAPABILITIES TABULATED

a. Are ultimate values under static conditions;

b. Do not include any other loading condition Pressure Panel Thickness Capability Remarks ID (in.)

(psi)

W-SL1 12 4.5 W-SL2 12 26.2 1 W-WN1 24 10.9 W-WN2 24 48.6 (1)

W-WS1 24 36.7 W-WS2 24 22.1 W-WS3 24 46.4 W-WS4 24 62.7 W-WS5 12 40.2 (1)

W-WS6 12 34.9 (1)

W-W1 12 27.3 W-W2 12 26.8 (1)

W-W3 36 54.9 W-W4 36 36.5 (1)

W-W5 36 84.5 W-W6 36 113.1 W-W7 36 121.6 (1)

See Figure 14.4.2-10 for wall and slab identification.

1 Indicates diagonal tension failure governs UNIT 2

UFSAR Revision 31.0 INDIANA MICHIGAN POWER Revision: 16.6 D. C. COOK NUCLEAR PLANT Table:14.4.6-16a UPDATED FINAL SAFETY ANALYSIS REPORT Page: 1 of 1 RELATION OF NODES USED IN WEST STEAM ENCLOSURE ANALYSIS TO PANEL IDENTIFICATION PRESENTED IN TABLE 14.4.6-16 Node No. 1 Affected Slabs 2 W-W3, W-W4, W-W5, W-WN1 3 W-WN1 4 W-WS1, W-WS2 5 W-W4, W-W5, W-WN1, W-SL1 6 W-W5, W-W6, W-WN2, W-SL2, W-WS6, W-WS5 11 W-W4, W-W5, W-SL1, W-WS2, W-WS3 12 W-WS1, W-WS2, W-W3, W-W4 1

Node numbers refer to Figure 14.4.6-1.

UNIT 2

UFSAR Revision 31.0 INDIANA MICHIGAN POWER Revision: 16.6 D. C. COOK NUCLEAR PLANT Table: 14.4.6-17 UPDATED FINAL SAFETY ANALYSIS REPORT Page: 1 of 1 PRESSURE CAPABILITY OF WALLS AND SLABS OF AUXILIARY BUILDING ADJACENT TO MAIN STEAM LINE ACCESSWAY

1. MATERIAL PROPERTIES

a. Concrete fc' = 3500 psi;

b. Reinforcing steel fy = 40000 psi

2. PRESSURE CAPABILITIES TABULATED

a. Are ultimate values under static conditions;

b. Do not include any other loading condition Pressure Panel Thickness Capability Remarks ID (in.)

(psi)

W-SL3 24 9.8 1 W-SL4 12 46.5 (1)

W-SL5 12 47.9 (1)

W-WN3 36 37.4 (1)

W-WN4 36 126.0 (1)

W-WS7 12 9.3 W-WS8 12 9.4 W-WS9 28 26.6 (1)

W-W8 12 15.7 W-W9 12 41.0 W-W10 42 30.0 W-W9A 12 38.4 See Figure 14.4.8-1 for layout and identification of walls and slabs.

1 Indicates diagonal tension failure governs UNIT 2

UFSAR Revision 31.0 INDIANA MICHIGAN POWER Revision: 16.4 D. C. COOK NUCLEAR PLANT Table: 14.4.6-18 UPDATED FINAL SAFETY ANALYSIS REPORT Page: 1 of 4 EFFECTS OF PRESSURES AND CIRCUMFERENTIAL BREAK IMPINGEMENT LOADS ON WALLS AND SLABS (1) PANELS AT MAIN STEAM LINES ENCLOSURE EAST OF CONTAINMENT Peak Peak Applied Required Allowable Panel Governing Applied Adequacy Impingement Ductility Ductility Remarks Identification Pipe Break Pressure of Panel Force (Kips) Factor Factor (Psi)

E-SL2 4F (MSB) 0 12.0 2.33 3.0 O.K.

E-SL3 4F (MSB) 0 12.0 1.00 3.0 O.K.

Assuming 4G has same pressure W-WN1 4G (MSB) 0 12.0 1.42 3.00 O.K.

build up as 4F E-WN2 4F (MSB) 0 12.0 1.00 3.00 O.K.

Assuming 1C has same pressure E-WN1 1C (MSB) 0 12.0 1.42 2.00 O.K.

build up as 1F E-WS2 1F (MSB) 0 12.0 1.00 3.00 O.K.

1F or 4F E-W1 (MSB) 0 12.0 2.13 3.00 O.K.

1F or 4F E-W2 (MSB) 0 12.0 1.00 3.00 O.K.

1F or 4F E-W3 (MSB) 0 12.0 1.51 3.00 O.K.

Assuming central portion of panel E-W4 1F or 4F 0 12.0 1.00 3.00 O.K. is allowed to fail, but the larger side portions are adequate UNIT 2

UFSAR Revision 31.0 INDIANA MICHIGAN POWER Revision: 16.4 D. C. COOK NUCLEAR PLANT Table: 14.4.6-18 UPDATED FINAL SAFETY ANALYSIS REPORT Page: 2 of 4 EFFECTS OF PRESSURES AND CIRCUMFERENTIAL BREAK IMPINGEMENT LOADS ON WALLS AND SLABS (2) PANELS AT MAIN STEAM LINES ENCLOSURE WEST OF CONTAINMENT Peak Applied Required Allowable Panel Governing Pipe Peak Applied Adequacy Impingement Ductility Ductility Remarks Identification Break Pressure (Psi) of Panel Force (Kips) Factor Factor 2E or 3E Slab modified and determined W-SL1 0 11.7 60.44 10.0 N.G (MSB) to be acceptable (see 14.4.9.1) 2E or 3E W-SL2 (MSB) 0 6.2 1.00 3.00 O.K.

Assuming 3D has same W-WN1 3D (MSB) 0 11.9 2.56 10.00 O.K.

pressure build up as 3E 2E or 3E W-WN2 (MSB) 0 6.2 1.00 3.00 O.K.

W-WS1 2E (MSB) 0 11.9 1.00 10.00 O.K.

Assuming 2D has same W-WS2 2D (MSB) 0 11.9 1.00 10.00 O.K.

pressure build up as 2E W-WS3 2E (MSB) 0 11. 7 1.00 10.00 O.K.

Not affected by any pipe break W-WS4 within the west enclosure 2E or 3E W-WS5 0 6.2 1.00 3.00 O.K.

(MSB) 2E or 3E W-WS6 0 6.2 1.00 3.00 O.K.

(MSB) 2E or 3E W-W1 0 6.2 1.00 10.0 O.K.

(MSB)

UNIT 2

UFSAR Revision 31.0 INDIANA MICHIGAN POWER Revision: 16.4 D. C. COOK NUCLEAR PLANT Table: 14.4.6-18 UPDATED FINAL SAFETY ANALYSIS REPORT Page: 3 of 4 EFFECTS OF PRESSURES AND CIRCUMFERENTIAL BREAK IMPINGEMENT LOADS ON WALLS AND SLABS (2) PANELS AT MAIN STEAM LINES ENCLOSURE WEST OF CONTAINMENT Peak Applied Required Allowable Panel Governing Pipe Peak Applied Adequacy Impingement Ductility Ductility Remarks Identification Break Pressure (Psi) of Panel Force (Kips) Factor Factor 2E or 3E W-W2 0 6.2 1.00 3.00 O.K.

(MSB) 2E or 3F W-W3 0 11.9 1.00 10.00 O.K.

(MSB) 2E or 3E W-W4 0 11.9 1.00 3.00 O.K.

(MSB) 2E or 3E W-W5 0 11.9 1.00 10.00 O.K.

(MSB) 2E or 3E W-W6 0 11.9 1.00 10.00 O.K.

(MSB)

UNIT 2

UFSAR Revision 31.0 INDIANA MICHIGAN POWER Revision: 16.4 D. C. COOK NUCLEAR PLANT Table: 14.4.6-18 UPDATED FINAL SAFETY ANALYSIS REPORT Page: 4 of 4 EFFECTS OF PRESSURES AND CIRCUMFERENTIAL BREAK IMPINGEMENT LOADS ON WALLS AND SLABS (3)

AUXILIARY BUILDING PANELS ADJACENT TO MAIN STEAM LINES ACCESSWAY Peak Applied Required Allowable Panel Governing Pipe Peak Applied Adequacy Impingement Ductility Ductility Remarks Identification Break Pressure (Psi) of Panel Force (Kips) Factor Factor W-SL3 F8 (FWB) 355 5.8 1.00 3.00 O.K.

W-SL4 F8 (FWB) 0 5.8 1.00 3.00 O.K.

W-SL5 F8 (FWB) 0 5.3 1.00 3.00 O.K.

W-WN3 F8 (FWB) 0 5.8 1.00 3.00 O.K.

W-WN4 F8 (FWB) 0 1.0 1.00 3.00 O.K.

W-WS7 F8 (FWB) 0 5.8 1.17 10.00 O.K.

W-WS8 F8 (FWB) 0 5.8 1.05 10.00 O.K.

W-WS9 F8 (FWB) 0 5.8 1.00 3.00 O.K.

W-W7 F8 (FWB) 0 5.8 1.00 3.00 O.K.

W-W8 F8 (FWB) 0 1.0 1.00 10.00 O.K.

W-W9 F8 (FWB) 0 1.0 1.00 10.00 O.K.

W-W9A F8 (FWB) 0 1.0 1.00 10.00 O.K.

Assuming F10 has W-W10 F10 (FWB) 355 5.1 1.00 10.00 O.K. same pressure build up as F8 (3)

MSB = main steam line break FWB = feedwater line break N.G. = no good UNIT 2

UFSAR Revision 31.0 INDIANA MICHIGAN POWER Revision: 16.6 D. C. COOK NUCLEAR PLANT Table: 14.4.6-19 UPDATED FINAL SAFETY ANALYSIS REPORT Page: 1 of 1 PANELS TO BE PROTECTED FROM MAIN STEAM LINE LONGITUDINAL BREAKS Longitudinal Breaks Panels To Be Protected Remarks 1F E-SL1, E-WN1, E-WS1 4F E-SL2, E-WN1, E-WS1 1G E-SL2, E-W1 4G E-SL2, E-W1 2E W-WS2, W-SL1, W-WN1 3E W-WS2, W-SL1, W-WN1 2D W-SL1, W-W4 3D W-SL1, W-W4 UNIT 2

UFSAR Revision 31.0 INDIANA MICHIGAN POWER Revision: 16.6 D. C. COOK NUCLEAR PLANT Table: 14.4.6-20 UPDATED FINAL SAFETY ANALYSIS REPORT Page: 1 of 1 FEEDWATER LINE BREAKS Longitudinal Breaks Panels To Be Protected Remarks F26, F25 E-SL2 F15, F16, F17 W-SL1 Calculations made for F15 F9, F10, F11, F12, F13 W-WS7 Calculations made for F9 only UNIT 2

UFSAR Revision 31.0 INDIANA MICHIGAN POWER Revision: 16.4 D. C. COOK NUCLEAR PLANT Table: 14.4.8-1 UPDATED FINAL SAFETY ANALYSIS REPORT Page 1 of 2 ULTIMATE SHEAR STRESS AT DISTANCE DE FROM THE SUPPORTS FOR TWO-WAY ELEMENTS I. THREE LIMITS ULTIMATE HORIZONTAL LIMITS ULTIMATE VERTICAL SHEAR EDGES FIXED SHEAR STRESS (Vµ)H STRESS(Vµ)r AND ONE EDGE FREE d x x d

2 3rµ 1 e 1 d e 3rµ 1 e H L HL 0 de / x 1 x 0 de / H 1 de 2 2 de 4d e 5 x x x x H 3 - 4d e L HL d x x d rµ 1 e 1 d e rµ 1 e H L HL 1 x 1 2

de / x 1 2 de / H 1 de d

2 e x x H1 2d e HL 2

2d y y d 3rµ 1 e 2 2d e 3rµ 1 e L H LH y 0 de / L 1 2d e 0 de / y 1 4 de y y d L 6 - 8d e y 5 - 4 e H LH y 2d y y rµ 1 e 2 2d e d L H LH rµ 1 e 1 1 1 y 4

de / L 2 4d e 2 de / y 1 2d e y

L1 2d e y LH UNIT 2

UFSAR Revision 31.0 INDIANA MICHIGAN POWER Revision: 16.4 D. C. COOK NUCLEAR PLANT Table: 14.4.8-1 UPDATED FINAL SAFETY ANALYSIS REPORT Page 2 of 2 II. FOUR EDGES NOTE: L MAY EITHER BE LONGER OR SHORTER THAN H FIXED 2 1 d x x d 3rµ e 1 2d e 3rµ 1 e 2 H L HL 0 de / x 1 x 0 de / H 1 de 2 4 d

d e x 5 - 4 e x H 3 - 8d e x

x L HL 1 d x x d rµ e 1 2d e rµ 1 e 2 H L HL 1 x 1 1 2

de / x 1 4 de / H 2 de de 2 x x H1 4d e HL rµ = ULTIMATE PRESSURE LOAD ON ELEMENT de = EFFECTIVE DEPTH OF ELEMENT NOTE: EXPRESSIONS IN THIS TABLE ARE TAKEN FROM REF. 2 UNIT 2

UFSAR Revision 31.0 INDIANA MICHIGAN POWER Revision: 16.4 D. C. COOK NUCLEAR PLANT Table: 14.4.8-2 UPDATED FINAL SAFETY ANALYSIS REPORT Page: 1 of 1 Material Properties Concrete: f'c = 3500 psi Reinforcing Steel: fy = 40,000 psi Ultimate Moment of 1 ft wide Rectangular Section T=C C = (0.85fc)(12)(0.85C) sf y C=

(0.85f ' c )(12)(0.85)

T= sfy Mu = T(d-0.425c)

After Substitutions, Mu = 3.33s(d-0.56s) (1)

Permissible Diagonal Tension Shear Stress

[ ]

Vc = 1.9 f ' c + 2500 2.28 f ' c (2)

Permissible Punching Shear Stress Vc = 4 f ' c (3)

Strength Increase Due to Dynamic Effects (Ref: 2)

(1) Where shear or diagonal tension governs, no increase is allowed.

(2) Where flexure governs, the following increases were used:

f'c = +25%, fy = +10%

Ultimate Moment of 1 ft Wide Rectangular Section: Mu = 3.67s(d-0.49s)

Unit 2

UFSAR Revision 31.0 INDIANA MICHIGAN POWER Revised: 29.0 D. C. COOK NUCLEAR PLANT Table:14.4.11-1 UPDATED FINAL SAFETY ANALYSIS REPORT Page: 1 of 1 Peak Environmental Qualification Conditions for LOCA, MSLB, and Feedwater Line Break Inside Containment LOCA Location Temperature (ºF) Pressure (psig)

Upper Compartment 1601 11.62 Lower Compartment 2353 11.62 Instrument and F/A Room 2354,3 13.95 MSLB and Feedwater Line Break Location Temperature (ºF) Pressure (psig)

Upper Compartment 135 (U1)6 , 128 (U2)6 20.85 Lower Compartment 3257 20.85 1

UFSAR Figure 14.3.4-7 2

UFSAR Figure 14.3.4-6A 3

UFSAR Figure 14.3.4-8 4

Deleted 5

UFSAR Table 14.3.4-40 reports this value calculated for the Steamline Break in the Steam Generator Doghouse.

The Steam Generator Doghouse peak pressure is a bounding value for Upper and Lower Containment.

6 UFSAR Figure 14.3.4-11 (Unit 1) and Figure 14.3.4-11A (Unit 2) 7 UFSAR Figure 14.3.4-12 (Unit 1) and Figure 14.3.4-12B (Unit 2)

Unit 2

UFSAR Revision 31.0 INDIANA MICHIGAN POWER Revision: 29.0 D. C. COOK NUCLEAR PLANT Table: 14.4.11-2 UPDATED FINAL SAFETY ANALYSIS REPORT Page: 1 of 1 AIRBORNE SOURCE TERM DOSES AND DOSE RATES Containment Centerline Dose Rates and Doses1 Time Gamma Dose Beta Dose Rate Total Dose Rate Gamma Dose Beta Dose Total Dose Rate [rad/hr[ [rad/hr[ [rad/hr] [rad] [rad] [rad]

1 second 4.293E+06 2.028E+07 2.46E+07 5.962E+02 2.817E+03 3.41E+03 30 minutes 1.905E+06 7.674E+06 9.58E+06 1.330E+06 5.196E+06 6.53E+06 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months 1.418E+06 6.592E+06 8.01E+06 2.145E+06 8.756E+06 1.09E+07 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months 9.818E+05 4.849E+06 5.83E+06 3.319E+06 1.443E+07 1.77E+07 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months 4.013E+05 1.508E+06 1.91E+06 6.889E+06 3.046E+07 3.73E+07 1 day 2.181E+05 5.753E+05 7.93E+05 1.131E+07 4.382E+07 5.51E+07 7 days 8.274E+04 2.350E+05 3.18E+05 3.014E+07 9.492E+07 1.25E+08 30 days 4.543E+03 1.708E+04 2.16E+04 4.480E+07 1.385E+08 1.83E+08 90 days 3.484E+01 5.456E+03 5.49E+03 4.580E+07 1.487E+08 1.94E+08 180 days 2.515E+01 5.352E+03 5.38E+03 4.586E+07 1.603E+08 2.06E+08 365 days 2.431E+01 5.175E+03 5.20E+03 4.597E+07 1.837E+08 2.30E+08 Inside Containment Wall Surface Dose Rates and Doses (1)

Time Gamma Dose Beta Dose Rate Total Dose Rate Gamma Dose Beta Dose Total Dose Rate [rad/hr[ [rad/hr[ [rad/hr] [rad] [rad] [rad]

1 second 3.408E+06 2.028E+07 2.37E+07 4.734E+02 2.817E+03 3.29E+03 30 minutes 1.906E+06 7.674E+06 9.58E+06 1.205E+06 5.196E+06 6.40E+06 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months 1.499E+06 6.592E+06 8.09E+06 2.046E+06 8.756E+06 1.08E+07 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months 1.080E+06 4.849E+06 5.93E+06 3.314E+06 1.443E+07 1.77E+07 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months 4.627E+05 1.508E+06 1.97E+06 7.346E+06 3.046E+07 3.78E+07 1 day 2.259E+05 5.753E+05 8.01E+05 1.228E+07 4.382E+07 5.61E+07 7 days 6.730E+04 2.350E+05 3.02E+05 2.832E+07 9.492E+07 1.23E+08 30 days 5.276E+03 1.708E+04 2.24E+04 4.141E+07 1.385E+08 1.80E+08 90 days 3.538E+01 5.456E+03 5.49E+03 4.274E+07 1.487E+08 1.91E+08 180 days 1.313E+01 5.352E+03 5.37E+03 4.277E+07 1.603E+08 2.03E+08 365 days 1.268E+01 5.175E+03 5.19E+03 4.283E+07 1.837E+08 2.27E+08 1

Per Calculation RS-C-0046 UNIT 2

UFSAR Revision 31.0 INDIANA MICHIGAN POWER Revision: 29.0 D. C. COOK NUCLEAR PLANT Table: 14.4.11-3 UPDATED FINAL SAFETY ANALYSIS REPORT Page: 1 of 1 SUBMERGED LOWER VOLUME / CONTAINMENT SUMP DOSE RATES & DOSES1 Beta Dose Gamma Dose Total Dose Gamma Dose Beta Dose Total Dose Time Rate Rate (rad/hr) Rate (rad/hr) (rad) (rad) (rad)

(rad/hr) 1 second 1.201E+06 1.791E+05 1.38E+06 1.668E+02 2.488E+01 1.92E+02 30 minutes 9.675E+05 1.388E+05 1.11E+06 5.377E+05 7.812E+04 6.16E+05 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months 8.100E+05 1.177E+05 9.28E+05 9.799E+05 1.418E+05 1.12E+06 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months 6.118E+05 9.462E+04 7.06E+05 1.682E+06 2.467E+05 1.93E+06 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months 2.834E+05 5.775E+04 3.41E+05 4.061E+06 6.719E+05 4.73E+06 1 day 1.315E+05 3.291E+04 1.64E+05 7.072E+06 1.364E+06 8.44E+06 7 days 3.467E+04 8.429E+03 4.31E+04 1.511E+07 3.346E+06 1.85E+07 30 days 9.922E+03 3.262E+03 1.32E+04 2.527E+07 6.123E+06 3.14E+07 90 days 3.470E+03 1.753E+03 5.22E+03 3.307E+07 9.351E+06 4.24E+07 180 days 1.733E+03 1.221E+03 2.95E+03 3.838E+07 1.249E+07 5.09E+07 365 days 7.349E+02 7.538E+02 1.49E+03 4.328E+07 1.673E+07 6.00E+07 1

Per Calculation RS-C-0046 UNIT 2

UFSAR Revision 31.0 INDIANA MICHIGAN POWER Revision: 29.0 D. C. COOK NUCLEAR PLANT Table: 14.4.11-4 UPDATED FINAL SAFETY ANALYSIS REPORT Page: 1 of 1 BETA DOSE FACTORS1 DOSE FROM AIRBORNE SOURCE AFTER ATTENUATION (PERCENTAGE OF DOSE PASSING THROUGH SHIELD)

Thickness of Unit Density Material (mils)

Time 10 20 30 40 50 60 70 1 second 78.68% 68.30% 60.73% 54.66% 49.58% 45.22% 41.38%

30 minutes 75.18% 64.48% 56.96% 51.04% 46.14% 41.94% 38.30%

1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months 75.37% 65.13% 57.92% 52.22% 47.48% 43.41% 39.83%

2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months 75.21% 65.41% 58.57% 53.16% 48.62% 44.71% 41.28%

8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months 70.04% 60.58% 54.41% 49.62% 45.62% 42.23% 39.24%

1 day 58.35% 48.97% 43.53% 39.50% 36.24% 33.49% 31.11%

7 days 31.56% 23.58% 20.49% 18.47% 16.88% 15.57% 14.44%

30 days 24.49% 16.73% 14.23% 12.73% 11.60% 10.68% 9.90%

90 days 24.78% 16.40% 13.60% 12.01% 10.87% 9.98% 9.24%

180 days 25.51% 16.28% 13.08% 11.34% 10.18% 9.30% 8.59%

365 days 26.67% 16.08% 12.22% 10.24% 9.03% 8.18% 7.52%

1 Per Calculation RS-C-0046 UNIT 2

UFSAR Revision 31.0 INDIANA MICHIGAN POWER Revision: 29.0 D. C. COOK NUCLEAR PLANT Table: 14.4.11-5 UPDATED FINAL SAFETY ANALYSIS REPORT Page: 1 of 1 BETA DOSE FACTORS1 DOSE FROM AIRBORNE SOURCE AFTER ATTENUATION (PERCENTAGE OF DOSE PASSING THROUGH SHIELD)

Thickness of Aluminum (mils)

Time 10 20 30 40 50 60 70 1 second 62.82% 47.77% 37.66% 30.25% 24.53% 20.03% 16.43%

30 minutes 59.01% 44.39% 34.79% 27.80% 22.49% 18.33% 15.05%

1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months 59.89% 45.77% 36.38% 29.42% 24.07% 19.84% 16.46%

2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months 60.44% 46.99% 37.93% 31.11% 25.77% 21.51% 18.05%

8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months 56.09% 44.21% 36.31% 30.30% 25.53% 21.64% 18.42%

1 day 44.98% 35.09% 28.78% 24.07% 20.33% 17.27% 14.74%

7 days 21.26% 16.33% 13.36% 11.16% 9.42% 8.00% 6.83%

30 days 14.81% 11.21% 9.15% 7.65% 6.45% 5.48% 4.68%

90 days 14.25% 10.50% 8.53% 7.12% 6.01% 5.11% 4.36%

180 days 13.81% 9.80% 7.93% 6.61% 5.58% 4.74% 4.04%

365 days 13.09% 8.65% 6.92% 5.77% 4.87% 4.14% 3.53%

1 Per Calculation RS-C-0046 UNIT 2

UFSAR Revision 31.0 INDIANA MICHIGAN POWER Revision: 29.0 D. C. COOK NUCLEAR PLANT Table: 14.4.11-6 UPDATED FINAL SAFETY ANALYSIS REPORT Page: 1 of 1 BETA DOSE FACTORS1 DOSE FROM AIRBORNE SOURCE AFTER ATTENUATION (PERCENTAGE OF DOSE PASSING THROUGH SHIELD)

Thickness of Steel (mils)

Time 10 20 30 40 50 60 70 1 second 38.44% 20.75% 11.76% 6.82% 4.01% 2.39% 1.43%

30 minutes 35.52% 19.00% 10.83% 6.41% 3.89% 2.41% 1.52%

1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months 37.10% 20.53% 12.05% 7.34% 4.59% 2.92% 1.88%

2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months 38.62% 22.20% 13.46% 8.42% 5.39% 3.50% 2.30%

8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months 36.91% 22.27% 14.05% 9.08% 5.96% 3.95% 2.64%

1 day 29.27% 17.77% 11.29% 7.33% 4.83% 3.22% 2.16%

7 days 13.58% 8.23% 5.23% 3.40% 2.24% 1.49% 1.00%

30 days 9.31% 5.64% 3.58% 2.33% 1.53% 1.02% 0.68%

90 days 8.68% 5.26% 3.34% 2.17% 1.43% 0.95% 0.64%

180 days 8.06% 4.88% 3.10% 2.01% 1.33% 0.88% 0.59%

365 days 7.05% 4.26% 2.70% 1.76% 1.16% 0.77% 0.52%

1 Per Calculation RS-C-0046 UNIT 2

UFSAR Revision 31.0 INDIANA MICHIGAN POWER Revision: 29.0 D. C. COOK NUCLEAR PLANT Table: 14.4.11-7 UPDATED FINAL SAFETY ANALYSIS REPORT Page: 1 of 1 PIPES CONSIDERED IN CALCULATING OUTSIDE CONTAINMENT DOSES1 Outside Diameter Wall Thickness, System Designation 2 OD/T OD (inches) T (inches)

CC M-14 4.5 0.438 10.3 CC M-14 3.5 0.438 7.99 CC M-14 2.0 0.344 5.81 CC B-14 6.625 0.134 49.44 CC B-14 8.625 0.148 58.28 SI K-14 4.5 0.337 13.35 SI B-14 4.5 0.12 37.5 SI B-14 6.625 0.134 49.44 SI K-14 2.375 0.276 8.61 SI K-14 1.9 0.2 9.5 SI K-14 1.05 0.154 6.82 RHR G-14 14.0 0.438 31.96 RHR G-14 3.5 0.216 16.20 RHR G-14 8.625 0.322 26.79 CS E-14 10.75 0.365 29.45 CS E-14 8.625 0.322 26.79 CS E-14 6.625 0.28 23.66 CS E-14 3.5 0.216 16.20 CS E-14 1.315 0.133 9.89 CS B-14 8.625 0.148 58.28 CS G-14 12.75 0.406 31.40 CS G-14 2.375 0.154 15.42 Key:

CC - Centrifugal Charging SI - Safety Injection RHR - Residual Heat Removal CS - Containment Spray 1

AEP: NRC: 05781, Attachment 4 2

Note: Pipe designation indicates materials of construction, seismic classification, and quality level. For further information, AEPSC specifications should be consulted.

UNIT 2

UFSAR Revision 31.0 INDIANA MICHIGAN POWER Revision: 29.0 D. C. COOK NUCLEAR PLANT Table: 14.4.11-8 UPDATED FINAL SAFETY ANALYSIS Page: 1 of 1 REPORT PEAK ENVIRONMENTAL QUALIFICATION CONDITIONS FOR HELB OUTSIDE CONTAINMENT COMPARTMENT TEMPERATURE (ºF) PRESSURE (psia)

East Main Steam Enclosure 440 18.7 West Main Steam Enclosure 485 20.6 Main Steam Accessway 347.8 18.2 Diesel Generator Pipe Tunnel 300 15.3 Turbine Driven Pump Room 298 16.7 ESW Tunnel 300 15.1 Turbine Room (Turbine Bldg. 609' Elev.) 473.8 15.45 Startup Blowdown Flashtank Room 216.5 15.2 NOTE:

Only major areas are identified in the table above.

UNIT 2

ML22340A161

Text

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